Abstract

The invention related to technology for manufacturing safety systems of nuclear power plants. A method for manufacturing a core catcher cantilever truss is characterized in that two symmetrical parts of the cantilever truss are formed, each of which is made of outer, middle, and inner half-shells, which are connected between each other with radial and parallel force ribs, as well as upper and lower semicircular force plates by welding, with formation of parallel and radial sectors. After that the above-mentioned two symmetrical parts are connected to each other by welding in the area of two parallel sectors located on one Cartesian axis, so that the upper horizontal connection connects the upper semicircular force plates, a lower horizontal welded joint connects the lower semicircular force plates, outer, inner, and middle vertical welded joints connect the outer, inner, and middle half-shells.

IPC Classes  ?

• B23K 31/02 - Processes relevant to this subclass, specially adapted for particular articles or purposes, but not covered by any single one of main groups relating to soldering or welding
• G21C 9/016 - Core catchers

Abstract

A thermal valve for a cooling fluid supply channel. The thermal valve comprises a body with a through channel to supply the cooling fluid through an inlet of the thermal valve in the direction of its outlet, and a fuse. The through channel is made in the form of an elbow and consists of a horizontal section and a downward-directed vertical section. The inlet is located in the lower part of the vertical section; the outlet of the through channel is provided with a plug made of high-strength refractory material and attached to a flange of the horizontal section with the fuse. The ratio of volumes of the horizontal and the vertical sections of the through channel is chosen so that a cooling fluid would neither enter the horizontal section of the through channel nor affect the melting point of the plug.

IPC Classes  ?

• F16K 17/38 - Safety valvesEqualising valves actuated in consequence of extraneous circumstances, e.g. shock, change of position of excessive temperature

Abstract

A tank for garbage filtration and collection. The tank for garbage filtration and collection comprises an inlet made in a tank cover, and an outlet, on which a filtering device is installed, a vertical shaft is installed in the inlet, installed on the bottom of the tank, a window is made in the lower part of the vertical shaft for liquid removal, directed to a side opposite to the filtering device, and the upper part of the vertical shaft is made in the form of a funnel. The tank for garbage filtration and collection can be used to filter a large fluid flow containing a large volume of garbage, particularly in nuclear power plant safety systems.

IPC Classes  ?

• B01D 21/00 - Separation of suspended solid particles from liquids by sedimentation
• B01D 29/085 - Funnel filtersHolders therefor
• B01D 29/90 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups Filtering elements therefor having feed or discharge devices for feeding
• B01D 35/027 - Filters adapted for location in special places, e.g. pipe-lines, pumps, stop-cocks rigidly mounted in or on tanks or reservoirs
• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat

Abstract

A limit stop for limiting the effect of severe accident consequences on process equipment connected by pipelines passing through walls. The stop may be used, in particular, in the nuclear industry. The limit stop installed in a protective wall. The stop is made in the form of an anchor with horizontal grooves and an insert into the pipeline with horizontal teeth. The anchor is mounted on a protective wall. The insert is installed on the pipeline from the outer side of the protective wall. The anchor and insert are made with the possibility of locking the teeth in the grooves during torsion. The insert is provided with a postulated break site.

IPC Classes  ?

• F16L 55/00 - Devices or appurtenances for use in, or in connection with, pipes or pipe systems

Abstract

The invention relates to core catchers, and more particularly to sacrificial packing for receiving and distributing nuclear reactor core melt. The technical result of the claimed invention is that of increasing the reliability of a core catcher by ensuring that cooling water is fed to the corium (core melt) inside the housing of the core catcher at a given calculated time after the moment when the corium enters the core catcher housing. This technical result is achieved in that the thermal shield of the core catcher housing is provided with an insert which provides for the protection of a water supply valve against the mechanical and thermal effects of corium, and which also makes it possible to set a calculated time at which water is supplied into the core catcher housing. The use of the claimed insert for a water supply valve (4) makes it possible to ensure that cooling water is fed into the core catcher housing at a given time determined by calculations.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to core catchers, and more particularly to sacrificial packing for receiving and distributing nuclear reactor core melt. The technical result consists in improving the reliability of a core catcher. This result is achieved by the use of a core catcher packing that contains plates of a material for diluting uranium-containing corium oxide which are joined by a cement mortar and arranged in a bottom steel unit, middle steel units and a top steel unit, wherein the bottom steel unit comprises a housing having a cover and a floor that tapers downwardly toward the centre, and a metallic structure consisting of a central hexagonal equilateral shell, the faces of which have radial sectors connected thereto, wherein one end of each sector is connected to one face of the shell, and arranged between the radial sectors and the walls of the housing are quadrilateral trapezoidal and hexagonal equilateral cells filled with shielding concrete and plates made of iron oxides and concrete.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to core catchers with a melt receiving and distributing vessel, and more particularly to mechanisms for maintaining the structural integrity of a core catcher in the event of a severe accident. The technical result of the claimed invention consists in improving the reliability of a core catcher support frame by creating a steam-gas distribution loop in the support frame using L-shaped and T-shaped connecting pipes connected to steam discharge pipes which, in turn, are connected to one another by recycling pipes.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

A pipe protection device relates to emergency protection systems for nuclear power plants, and more particularly to devices for protecting pipes for passively filling the shaft of a core catcher, and can be used in the event of severe accidents that result in damage to the reactor vessel, as well as in other technical fields in which filter elements are used.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to core catchers with a melt receiving and distributing vessel, and more particularly to mechanisms for maintaining the structural integrity of a core catcher in the event of a severe accident. The technical result of the claimed invention consists in improving the reliability of a core catcher. The claimed invention seeks to solve the problem of providing for steady cooling of a support frame in a reactor shaft in order to prevent damage to the support frame in the event of beyond design-basis accidents entailing exposure to thermal radiation from the melt mirror and the convection transfer of heat from a steam-gas medium. The problem of interest is solved by embodiments of a core catcher support frame in which first, second and third groups of connecting pipes are used which allow circulation of the steam-gas medium during the containment and cooling of nuclear reactor core melt.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to core catchers with a melt receiving and distributing vessel, and more particularly to mechanisms for maintaining the structural integrity of a core catcher in the event of a severe accident. The technical result of the claimed invention consists in improving the reliability of a core catcher by means of a water coolant loop that is formed by installing in the support frame a water collector, to which are linked water feed connecting pipes connected to water feed pipes, wherein butted into said connecting pipes from below are distributing connecting pipes with spraying devices on the ends thereof. In one embodiment, the support frame can have two water collectors installed therein.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

A system for confining and cooling melt from the core of a nuclear reactor comprises a guide device, a cantilever truss, a filler for receiving and distributing melt. The filler being disposed in a housing having water supply valves mounted around its perimeter and having a flange with a thermal shield mounted thereon. A drum is mounted on the flange and comprises reinforcing ribs mounted around its perimeter on the inner side. The reinforcing ribs bear against a cover and a bottom. The drum comprises tensioning elements connecting the drum, via a support flange, to the flange of the housing, and spacing elements providing an adjustment gap between the drum and the flange of the housing. The drum comprises nozzles equipped with heat reflectors, cooling ribs, and water supply valves mounted for increasing the reliability of the system for confining and cooling melt from the core of a nuclear reactor.

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat

Abstract

A water supply valve comprises an actuating sleeve inserted in an intermediate sleeve and bearing on said intermediate sleeve by means of flanged stops, an actuating rod with a piston, said actuating rod being mounted inside the actuating sleeve and the intermediate sleeve so that the actuating rod bears, via the piston, on a thermomechanical element which bears, via a pressure mechanism, on a protective membrane fastened in the end of the actuating sleeve, an actuating spring mounted on the actuating rod so that one end of the spring bears on the piston and the other end bears on the flanged stops of the actuating sleeve, a rolling bearing mounted on the end of the actuating rod which projects from the actuating sleeve, a flanged cylinder in which is inserted a flanged sleeve with a rod-type sleeve mounted therein, the latter receiving a stem with a thread and with a control valve, said stem being rollably mounted, and a thrust sleeve in which are mounted a flanged thrust rod and a working spring, one end of which bears on the flanges of the thrust rod and the other end of which bears on the thrust sleeve, wherein mounted between the control valve and the thrust rod is a ball bearing.

IPC Classes  ?

• F16K 17/38 - Safety valvesEqualising valves actuated in consequence of extraneous circumstances, e.g. shock, change of position of excessive temperature

Abstract

A system for confining and cooling melt from the core of a nuclear reactor comprises a guide device, a cantilever truss, a filler for receiving and distributing melt. The filler being disposed in a housing having water supply valves mounted around its perimeter and having a flange with a thermal shield mounted thereon. A drum is mounted on the flange and comprises reinforcing ribs mounted bearing against a cover and a bottom. The drum comprises tensioning elements connecting the drum, via a support flange, to the flange of the housing, and spacing elements. The drum comprises nozzles having water supply valves mounted therein with sealed covers, and hydraulic dampers connected to external sources of water and to the water supply valves by feed pipes, pressure pipes, compensating pipes and equalizing pipes, for increasing the reliability of the system for confining and cooling melt from the core of a nuclear reactor.

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 13/10 - Means for preventing contamination in event of leakage

Abstract

Systems for ensuring safety of nuclear power plants (NPPs). The systems enhance reliability of the corium localizing and cooling system of a nuclear reactor. The corium localizing and cooling system comprise thermal protection suspended to the cantilever truss, the membrane installed between the cantilever truss and the vessel, and the bandage plates installed on the external and internal side of the membrane. The systems prevent destruction of the corium localizing and cooling system within the junction area between the vessel for the corium receipt and distribution and the cantilever truss under the conditions on non-axisymmetric corium escape from the reactor pressure vessel and falling of the reactor pressure vessel head fragments into the vessel at the initial stage of the corium cooling with water, and consequently to prevent any ingress of water intended for external cooling of the vessel into the vessel.

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat

Abstract

Systems ensuring safety of nuclear power plants (NPPs) used in severe accidents resulting in destruction of the reactor pressure vessel and containment. The technical result of the claimed invention is to enhance reliability of the corium localizing and cooling system of a nuclear reactor. The technical result is achieved due to use of the membrane installed between the cantilever truss and the vessel, bandage plates installed on the external and internal side of the membrane, the hydraulic gas-dynamic damper installed on the internal side of the membrane in the corium localizing and cooling system of a nuclear reactor enabling to prevent any destruction within the leak-tight junction area between the multi-layered vessel and the cantilever truss under the conditions with non-axisymmetric corium flow from the reactor pressure vessel and falling of reactor pressure vessel head fragments into the vessel at the initial stage of the corium cooling with water.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

Systems for ensuring safety of nuclear power plants (NPPs), and can be used in severe accidents resulting in destruction of the reactor pressure vessel and containment. The systems enhance reliability of the corium localizing and cooling system of a nuclear reactor. The technical result is achieved due to prevention of the corium localizing and cooling system destruction in the junction area between the vessel and the cantilever truss by use of a membrane with bandage plates installed on the drum within the system.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

A single-use emergency thermal valve relates to valves that open a channel for supplying a cooling liquid in the event of an emergency. The present single-use emergency thermal valve comprises a housing having a through-channel therein for supplying a cooling liquid through an inlet opening in the thermal valve toward an outlet opening, and a safety fuse, the melting point of which is selected according to the activation temperature of the valve, wherein the through-channel is configured in the form of an elbow bend and consists of a horizontal portion and a downwardly oriented vertical portion, the inlet opening of the channel is disposed in the bottom part of the vertical portion, the outlet opening of the through-channel is provided with a plug made of a high-strength material with a high melting point, which is fastened to a flange of the horizontal portion by means of the safety fuse, and wherein the ratio of the volume of the horizontal portion to the volume of the vertical portion of the through-channel is selected so that cooling liquid does not enter the horizontal portion of the through-channel and does not affect the melting temperature of the plug. The single-use emergency thermal valve can be used in various fields of industry requiring the release of a cooling liquid in the event of an emergency, in particular, the nuclear industry.

IPC Classes  ?

• F16K 17/38 - Safety valvesEqualising valves actuated in consequence of extraneous circumstances, e.g. shock, change of position of excessive temperature
• F16K 17/40 - Safety valvesEqualising valves with fracturing member, e.g. fracturing diaphragm, fusible joint

Abstract

The invention relates to a self-cleaning liquid purification system and is designed for the use in sump tank filters in nuclear power plants, as well as in any submersible filters used in any sectors of the economy. A self-cleaning liquid purification system comprises a filtration unit with filtering elements, a clean liquid discharge pipe, and an aerator. The aerator is designed as an intake device located on the liquid-gas boundary in a source of liquid to be purified, the aerator is capable of forming a liquid-gas mixture when it enters the intake device. The aerator is connected with a vertical downcomer to an accumulation chamber that is connected to the filtration unit by a hydraulic lock that is designed to be capable of pulse feed of liquid-gas mixture. The technical result is improved operation reliability of the liquid purification system through ensuring its capability of self-cleaning in the passive mode.

IPC Classes  ?

• G21D 1/02 - Arrangements of auxiliary equipment
• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat

Abstract

A single-use emergency thermal valve relates to valves that open a channel for supplying a cooling liquid in the event of an emergency. The present single-use emergency thermal valve comprises a housing having a through-channel therein for supplying a cooling liquid through an inlet opening in the thermal valve toward an outlet opening, and a safety fuse, the melting point of which is selected according to the activation temperature of the valve, wherein the through-channel is configured in the form of an elbow bend and consists of a horizontal portion and a downwardly oriented vertical portion, the inlet opening of the channel is disposed in the bottom part of the vertical portion, the outlet opening of the through-channel is provided with a plug made of a high-strength material with a high melting point, which is fastened to a flange of the horizontal portion by means of the safety fuse, and wherein the ratio of the volume of the horizontal portion to the volume of the vertical portion of the through-channel is selected so that cooling liquid does not enter the horizontal portion of the through-channel and does not affect the melting temperature of the plug. The single-use emergency thermal valve can be used in various fields of industry requiring the release of a cooling liquid in the event of an emergency, in particular, the nuclear industry.

IPC Classes  ?

• F16K 17/40 - Safety valvesEqualising valves with fracturing member, e.g. fracturing diaphragm, fusible joint
• F16K 17/38 - Safety valvesEqualising valves actuated in consequence of extraneous circumstances, e.g. shock, change of position of excessive temperature

Abstract

The invention relates to technology for manufacturing safety systems for nuclear power plants. A method for manufacturing a core catcher support frame is characterized in that two symmetrical parts of the support frame are formed, each of which is comprised of an outer half-shell, a middle half-shell, and an inner half-shell, which are connected to one another by radial and parallel strengthening ribs, as well as by an upper semi-circular strengthening plate and a lower semi-circular strengthening plate by means of welding to form parallel and radial sectors. The two symmetrical parts are then welded to one another in the region of two parallel sectors disposed on a single Cartesian axis, so that an upper horizontal join connects the upper semi-circular strengthening plates, a lower horizontal weld join connects the lower semi-circular strengthening plates, and vertical outer, inner and middle weld joins connect the outer, inner and middle half-shells. This increases the reliability of a device for catching and cooling molten core of a nuclear reactor.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

A restraining seal relates to devices for limiting the impact of serious accidents on technical equipment connected by pipes which pass through walls and is applicable, in particular, in the nuclear power sector. The present restraining seal, which can be mounted in a protective wall, is configured in the form of an anchoring member having horizontal grooves, which is mounted on the protective wall, and an insert having horizontal teeth, which is mounted on a pipe from the outer side of the protective wall, said anchoring member and insert being configured so that the teeth are capable of engaging in the grooves under twisting. In addition, the insert is provided with a postulated rupture point. The restraining seal makes it possible to increase the operating safety of high-pressure pipes and can be used in the energy industry.

IPC Classes  ?

• F16L 57/00 - Protection of pipes or objects of similar shape against external or internal damage or wear
• G21C 9/00 - Emergency protection arrangements structurally associated with the reactor

Abstract

A tank for filtering and collecting debris relates to devices for filtering large volumes of liquid which contain debris, and can be used, in particular, in the nuclear industry and specifically in sump tanks in nuclear power plants, designed to filter large volumes of coolant in the event of an accident. A tank for filtering and collecting debris comprises an inlet opening provided in a lid of the tank, and an outlet opening having a filter device mounted thereon, wherein the inlet opening has a vertical shaft arranged therein which is mounted on the bottom of the tank, the lower part of the vertical shaft has a port for the egress of liquid, said port being oriented in a direction opposite to the filter device, and the upper part of the vertical shaft is configured in the form of a funnel. The tank for filtering and collecting debris can be used for filtering a large flow of liquid containing a large volume of debris, in particular, in nuclear power plant safety systems.

IPC Classes  ?

• B01D 21/00 - Separation of suspended solid particles from liquids by sedimentation
• B01D 29/86 - Retarding cake deposition on the filter during the filtration period, e.g. using stirrers

Abstract

A restraining seal relates to devices for limiting the impact of serious accidents on technical equipment connected by pipes which pass through walls and is applicable, in particular, in the nuclear power sector. The present restraining seal, which can be mounted in a protective wall, is configured in the form of an anchoring member having horizontal grooves, which is mounted on the protective wall, and an insert having horizontal teeth, which is mounted on a pipe from the outer side of the protective wall, said anchoring member and insert being configured so that the teeth are capable of engaging in the grooves under twisting. In addition, the insert is provided with a postulated rupture point. The restraining seal makes it possible to increase the operating safety of high-pressure pipes and can be used in the energy industry.

IPC Classes  ?

• F16L 57/00 - Protection of pipes or objects of similar shape against external or internal damage or wear
• G21C 9/00 - Emergency protection arrangements structurally associated with the reactor

Abstract

A tank for filtering and collecting debris relates to devices for filtering large volumes of liquid which contain debris, and can be used, in particular, in the nuclear industry and specifically in sump tanks in nuclear power plants, designed to filter large volumes of coolant in the event of an accident. A tank for filtering and collecting debris comprises an inlet opening provided in a lid of the tank, and an outlet opening having a filter device mounted thereon, wherein the inlet opening has a vertical shaft arranged therein which is mounted on the bottom of the tank, the lower part of the vertical shaft has a port for the egress of liquid, said port being oriented in a direction opposite to the filter device, and the upper part of the vertical shaft is configured in the form of a funnel. The tank for filtering and collecting debris can be used for filtering a large flow of liquid containing a large volume of debris, in particular, in nuclear power plant safety systems.

IPC Classes  ?

• B01D 21/00 - Separation of suspended solid particles from liquids by sedimentation
• B01D 29/86 - Retarding cake deposition on the filter during the filtration period, e.g. using stirrers

Abstract

The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to reactor pressure vessel and its containment destruction. The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to reactor pressure vessel and its containment destruction. The technical result of the claimed invention consists in increasing the reliability of the corium localizing and cooling system of the nuclear reactor, increase of heat removal efficiency from corium of the nuclear reactor. The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to reactor pressure vessel and its containment destruction. The technical result of the claimed invention consists in increasing the reliability of the corium localizing and cooling system of the nuclear reactor, increase of heat removal efficiency from corium of the nuclear reactor. The technical result is achieved by using upper heat insulation in the corium localizing and cooling system of the nuclear reactor, installed in the area between the reactor pressure vessel and cantilever truss, and lower thermal protection installed inside the reactor pressure vessel on the filler upper cassette.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to reactor pressure vessel and its containment destruction. The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to reactor pressure vessel and its containment destruction. The technical result of the claimed invention consists in increasing the reliability of the corium localizing and cooling system of a nuclear reactor, increase of heat removal efficiency from corium of a nuclear reactor. The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to reactor pressure vessel and its containment destruction. The technical result of the claimed invention consists in increasing the reliability of the corium localizing and cooling system of a nuclear reactor, increase of heat removal efficiency from corium of a nuclear reactor. The technical result is achieved through the use of the membrane and thermal shield installed in the area between the multilayer casing and the cantilever truss in the corium localizing and cooling system of a nuclear reactor.

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat

Abstract

The invention is applicable to the corium localizing and cooling systems of a nuclear reactor designed for localization of severe beyond design-basis accidents, in particular, to the devices for directing corium of a nuclear reactor to the corium trap. The invention is applicable to the corium localizing and cooling systems of a nuclear reactor designed for localization of severe beyond design-basis accidents, in particular, to the devices for directing corium of a nuclear reactor to the corium trap. The technical result of the claimed invention is to increase the efficiency of localization and cooling of the nuclear reactor core melt. The invention is applicable to the corium localizing and cooling systems of a nuclear reactor designed for localization of severe beyond design-basis accidents, in particular, to the devices for directing corium of a nuclear reactor to the corium trap. The technical result of the claimed invention is to increase the efficiency of localization and cooling of the nuclear reactor core melt. The goal of the invention is to eliminate the guide assembly failure due to the concentration of impact load in the conical part of the guide assembly and, therefore, the instantaneous penetration of the core, fragments of the reactor vessel internals and the reactor vessel head into the core catcher. The invention is applicable to the corium localizing and cooling systems of a nuclear reactor designed for localization of severe beyond design-basis accidents, in particular, to the devices for directing corium of a nuclear reactor to the corium trap. The technical result of the claimed invention is to increase the efficiency of localization and cooling of the nuclear reactor core melt. The goal of the invention is to eliminate the guide assembly failure due to the concentration of impact load in the conical part of the guide assembly and, therefore, the instantaneous penetration of the core, fragments of the reactor vessel internals and the reactor vessel head into the core catcher. In accordance with the invention, the guide assembly of the corium localizing and cooling system installed under the reactor pressure vessel and resting on the cantilever truss apart from the load-bearing frame contains the thermal elements that in the aggregate allows providing guaranteed entry of core, debris of the internals and the head of the reactor pressure vessel into the corium trap by excluding melt-through of the walls of conical and cylindrical parts and by redistributing the corium jet streams.

IPC Classes  ?

• G21C 13/10 - Means for preventing contamination in event of leakage
• G21C 9/016 - Core catchers

Abstract

The invention is applicable to the corium localizing and cooling systems of a nuclear reactor designed for localization of severe beyond design-basis accidents, in particular, to the devices for directing corium of a nuclear reactor to the corium trap. The technical result of the claimed invention is to increase the efficiency of localization and cooling of the nuclear reactor core melt. The invention is applicable to the corium localizing and cooling systems of a nuclear reactor designed for localization of severe beyond design-basis accidents, in particular, to the devices for directing corium of a nuclear reactor to the corium trap. The technical result of the claimed invention is to increase the efficiency of localization and cooling of the nuclear reactor core melt. The goal of the invention is to eliminate the guide assembly failure due to the concentration of impact load in the conical part of the guide assembly and, therefore, the instantaneous penetration of the core, fragments of the reactor vessel internals and the reactor vessel head into the core catcher. The invention is applicable to the corium localizing and cooling systems of a nuclear reactor designed for localization of severe beyond design-basis accidents, in particular, to the devices for directing corium of a nuclear reactor to the corium trap. The technical result of the claimed invention is to increase the efficiency of localization and cooling of the nuclear reactor core melt. The goal of the invention is to eliminate the guide assembly failure due to the concentration of impact load in the conical part of the guide assembly and, therefore, the instantaneous penetration of the core, fragments of the reactor vessel internals and the reactor vessel head into the core catcher. According to the claimed invention, the guide assembly of the nuclear reactor corium localizing and cooling system installed under the reactor vessel and supported on the cantilever truss contains a cylindrical part, a conical part with an opening made in it, with their walls covered with heat-resistant and fusible material and divided into sectors by bearing ribs arranged radially relative to the opening, and a bearing frame consisting of the outer upper bearing ring, the outer lower bearing ring, the inner bearing shell, the outer upper bearing shell, the middle bearing shell divided into sectors by bearing ribs, the outer lower bearing shell, support ribs, base, upper inclined plate connecting the conical head, bearing ribs and the middle bearing shell, lower inclined plate connecting the conical head, bearing ribs, the middle bearing shell and the outer upper bearing shell. The invention is applicable to the corium localizing and cooling systems of a nuclear reactor designed for localization of severe beyond design-basis accidents, in particular, to the devices for directing corium of a nuclear reactor to the corium trap. The technical result of the claimed invention is to increase the efficiency of localization and cooling of the nuclear reactor core melt. The goal of the invention is to eliminate the guide assembly failure due to the concentration of impact load in the conical part of the guide assembly and, therefore, the instantaneous penetration of the core, fragments of the reactor vessel internals and the reactor vessel head into the core catcher. According to the claimed invention, the guide assembly of the nuclear reactor corium localizing and cooling system installed under the reactor vessel and supported on the cantilever truss contains a cylindrical part, a conical part with an opening made in it, with their walls covered with heat-resistant and fusible material and divided into sectors by bearing ribs arranged radially relative to the opening, and a bearing frame consisting of the outer upper bearing ring, the outer lower bearing ring, the inner bearing shell, the outer upper bearing shell, the middle bearing shell divided into sectors by bearing ribs, the outer lower bearing shell, support ribs, base, upper inclined plate connecting the conical head, bearing ribs and the middle bearing shell, lower inclined plate connecting the conical head, bearing ribs, the middle bearing shell and the outer upper bearing shell. 3 claims, 4 figures of drawings

IPC Classes  ?

• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat
• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to reactor pressure vessel and its containment destruction. The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to reactor pressure vessel and its containment destruction. The technical result of the claimed invention consists in increasing the reliability of the corium localizing and cooling system of a nuclear reactor, increase of heat removal efficiency from corium of a nuclear reactor. The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to reactor pressure vessel and its containment destruction. The technical result of the claimed invention consists in increasing the reliability of the corium localizing and cooling system of a nuclear reactor, increase of heat removal efficiency from corium of a nuclear reactor. The technical result is achieved by using the membraned, drum and thermal protection installed in the area between the layered vessel and cantilever truss in the corium localizing and cooling system of a nuclear reactor.

IPC Classes  ?

• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat

Abstract

The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. A system for confining and cooling melt from the core of a nuclear reactor comprises a guide device, a cantilever truss, a filler for receiving and distributing melt, said filler being disposed in a housing having water supply valves mounted around its perimeter and having a flange with a thermal shield mounted thereon, a drum mounted on the flange of said housing and being configured in the form of a casing with reinforcing ribs mounted around its perimeter on the inner side, said reinforcing ribs bearing against a cover and a bottom, wherein said drum has tensioning elements connecting the drum, via a support flange welded thereto, to the flange of the housing, and spacing elements providing an adjustment gap between the drum and the flange of the housing. Provided in the drum are nozzles equipped with heat reflectors and cooling ribs and having water supply valves mounted therein, for increasing the reliability of the system for confining and cooling melt from the core of a nuclear reactor.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

A water supply valve comprises an actuating sleeve inserted in an intermediate sleeve and bearing on said intermediate sleeve by means of flanged stops, an actuating rod with a piston, said actuating rod being mounted inside the actuating sleeve and the intermediate sleeve so that the actuating rod bears, via the piston, on a thermomechanical element which bears, via a pressure mechanism, on a protective membrane fastened in the end of the actuating sleeve, an actuating spring mounted on the actuating rod so that one end of the spring bears on the piston and the other end bears on the flanged stops of the actuating sleeve, a rolling bearing mounted on the end of the actuating rod which projects from the actuating sleeve, a flanged cylinder in which is inserted a flanged sleeve with a rod-type sleeve mounted therein, the latter receiving a stem with a thread and with a control valve, said stem being rollably mounted, and a thrust sleeve in which are mounted a flanged thrust rod and a working spring, one end of which bears on the flanges of the thrust rod and the other end of which bears on the thrust sleeve, wherein mounted between the control valve and the thrust rod is a ball bearing.

IPC Classes  ?

• F16K 17/38 - Safety valvesEqualising valves actuated in consequence of extraneous circumstances, e.g. shock, change of position of excessive temperature
• F16K 17/40 - Safety valvesEqualising valves with fracturing member, e.g. fracturing diaphragm, fusible joint
• G21C 15/24 - Promoting flow of the coolant

Abstract

The invention relates to systems which provide for the safety of nuclear power plants, and can be used in the event of accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. A system for confining and cooling melt from the core of a nuclear reactor comprises a guide device, a cantilever truss, a filler for receiving and distributing melt, said filler being disposed in a housing having water supply valves mounted around its perimeter and having a flange with a thermal shield mounted thereon, a drum mounted on the flange of said housing and being configured in the form of a casing with reinforcing ribs mounted around its perimeter on the inner side, said reinforcing ribs bearing against a cover and a bottom, wherein said drum has tensioning elements connecting the drum, via a support flange welded thereto, to the flange of the housing, and spacing elements. Provided in the drum are nozzles having water supply valves mounted therein with sealed covers, and hydraulic dampers connected to external sources of water and to the water supply valves by feed pipes, pressure pipes, compensating pipes and equalizing pipes, for increasing the reliability of the system for confining and cooling melt from the core of a nuclear reactor.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

A water supply valve comprises an actuating sleeve inserted in an intermediate sleeve and bearing on said intermediate sleeve by means of flanged stops, an actuating rod with a piston, said actuating rod being mounted inside the actuating sleeve and the intermediate sleeve so that the actuating rod bears, via the piston, on a thermomechanical element which bears, via a pressure mechanism, on a protective membrane fastened in the end of the actuating sleeve, an actuating spring mounted on the actuating rod so that one end of the spring bears on the piston and the other end bears on the flanged stops of the actuating sleeve, a rolling bearing mounted on the end of the actuating rod which projects from the actuating sleeve, a flanged cylinder in which is inserted a flanged sleeve with a rod-type sleeve mounted therein, the latter receiving a stem with a thread and with a control valve, said stem being rollably mounted, and a thrust sleeve in which are mounted a flanged thrust rod and a working spring, one end of which bears on the flanges of the thrust rod and the other end of which bears on the thrust sleeve, wherein mounted between the control valve and the thrust rod is a ball bearing.

IPC Classes  ?

• F16K 17/40 - Safety valvesEqualising valves with fracturing member, e.g. fracturing diaphragm, fusible joint
• F16K 17/38 - Safety valvesEqualising valves actuated in consequence of extraneous circumstances, e.g. shock, change of position of excessive temperature
• G21C 15/24 - Promoting flow of the coolant

Abstract

The invention relates to systems which provide for the safety of nuclear power plants, and can be used in the event of accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. A system for confining and cooling melt from the core of a nuclear reactor comprises a guide device, a cantilever truss, a filler for receiving and distributing melt, said filler being disposed in a housing having water supply valves mounted around its perimeter and having a flange with a thermal shield mounted thereon, a drum mounted on the flange of said housing and being configured in the form of a casing with reinforcing ribs mounted around its perimeter on the inner side, said reinforcing ribs bearing against a cover and a bottom, wherein said drum has tensioning elements connecting the drum, via a support flange welded thereto, to the flange of the housing, and spacing elements. Provided in the drum are nozzles having water supply valves mounted therein with sealed covers, and hydraulic dampers connected to external sources of water and to the water supply valves by feed pipes, pressure pipes, compensating pipes and equalizing pipes, for increasing the reliability of the system for confining and cooling melt from the core of a nuclear reactor.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. The aim of the invention is to prevent a system for confining and cooling melt from being destroyed in the zone where a housing for receiving and distributing melt is connected to a cantilever truss in the event that melt escapes from the pressure vessel in an axially asymmetric fashion and fragments of the bottom of the pressure vessel fall into the multilayer housing in the initial stage of the water cooling of the melt, and thus to prevent cooling water intended for cooling the outside of the housing from entering same. This aim is achieved in that a system for confining and cooling melt from the core of a nuclear reactor additionally comprises a heat shield suspended from the cantilever truss, a membrane mounted between the cantilever truss and the housing, and banding plates mounted on the inner and outer sides of said membrane.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. The technical result of the claimed invention is an increase in the reliability of a system for confining and cooling melt from the core of a nuclear reactor. This technical result is achieved in that a system for confining and cooling melt from the core of a nuclear reactor comprises a membrane installed between a cantilever truss and a housing, shroud plates installed on the outer and inner sides of the membrane, and a hydro- and gas dynamic damper installed on the inner side of the membrane, which makes it possible to prevent damage in the zone where the multilayer housing is connected to the cantilever truss in the event that melt escapes in an axially asymmetric fashion from the pressure vessel and fragments of the bottom of the pressure vessel fall into the housing in the initial stage of the water cooling of the melt.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. The technical result of the claimed invention is an increase in the reliability of a system for confining and cooling melt from the core of a nuclear reactor. This technical result is achieved in that a system for confining and cooling melt from the core of a nuclear reactor comprises a membrane installed between a cantilever truss and a housing, shroud plates installed on the outer and inner sides of the membrane, and a hydro- and gas dynamic damper installed on the inner side of the membrane, which makes it possible to prevent damage in the zone where the multilayer housing is connected to the cantilever truss in the event that melt escapes in an axially asymmetric fashion from the pressure vessel and fragments of the bottom of the pressure vessel fall into the housing in the initial stage of the water cooling of the melt.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. The technical result of the claimed invention is an increase in the reliability of a system for confining and cooling melt from the core of a nuclear reactor. This technical result is achieved by preventing a system for confining and cooling melt from being destroyed in the zone where a housing and a cantilever truss are connected by using in said system a membrane with banding plates, which is mounted on a drum.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. The aim of the invention is to prevent a system for confining and cooling melt from being destroyed in the zone where a housing for receiving and distributing melt is connected to a cantilever truss in the event that melt escapes from the pressure vessel in an axially asymmetric fashion and fragments of the bottom of the pressure vessel fall into the multilayer housing in the initial stage of the water cooling of the melt, and thus to prevent cooling water intended for cooling the outside of the housing from entering same. This aim is achieved in that a system for confining and cooling melt from the core of a nuclear reactor additionally comprises a heat shield suspended from the cantilever truss, a membrane mounted between the cantilever truss and the housing, and banding plates mounted on the inner and outer sides of said membrane.

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat

Abstract

The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. The technical result of the claimed invention is an increase in the reliability of a system for confining and cooling melt from the core of a nuclear reactor. This technical result is achieved by preventing a system for confining and cooling melt from being destroyed in the zone where a housing and a cantilever truss are connected by using in said system a membrane with banding plates, which is mounted on a drum.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to safe operation support systems of nuclear power plants (NPPs) at severe accidents, including methods and systems for cooling and cooling control of the reactors molten core. The invention increases safety of NPP and cooling efficiency of the molten core of a reactor. The invention increases the efficiency of cooling the molten core of a reactor by safely removing the heat load from the molten metal mirror, ensuring the elimination of vapor explosions. The invention changes the principle of cooling the reactor molten core, in that after the molten core destroys the reactor vessel, the conditions for subsequent cooling of the molten metal are determined by the characteristics of the trap casing, but not of the reactor.

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat
• G21C 17/112 - Measuring temperature
• G21C 19/04 - Means for controlling flow of coolant over objects being handledMeans for controlling flow of coolant through channel being serviced
• G21C 17/00 - MonitoringTesting
• G21C 9/00 - Emergency protection arrangements structurally associated with the reactor
• G21C 19/313 - Arrangements for introducing fluent material into the reactor coreArrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for liquids for molten metals using cold traps

Abstract

The invention relates to pipelines and equipment useful in nuclear power plants, heat power engineering, manufacturing engineering, petrochemistry, water supply, chemical and aerospace industries, and other fields. The invention relates to a pipe heat insulation casing consisted of metal elements and assembly method ensuring reliable electrical insulation of all elements. The connection of the metal elements is with lapping, the elements are with openings in the lapping area where the electrically-insulating spacers are set made of resilient, elastic-plastic, plastic, fully viscous or partially solidified material ensuring electrical insulation between the adjacent elements. The electrically-insulating spacers are applied to the lapping areas of the metal elements to fill the openings of the lapping areas thus arranging reliable pin connections between the spacer and adjacent casing elements. Multiple pin connections ensure fixation of the adjacent metal elements without any failure to electrical insulation of each other.

IPC Classes  ?

• F16L 9/14 - Compound tubes, i.e. made of materials not wholly covered by any one of the preceding groups
• F16L 59/10 - Bandages or covers for the protection of the insulation, e.g. against the influence of the environment or against mechanical damage
• F16L 59/14 - Arrangements for the insulation of pipes or pipe systems
• G01M 3/18 - Investigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using electric detection means for pipes, cables, or tubesInvestigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using electric detection means for pipe joints or sealsInvestigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using electric detection means for valves

Abstract

The invention relates to systems for confining and cooling the melt from the core of a nuclear reactor, which are intended to contain severe beyond design-basis accidents, more particularly devices for guiding the melt from the nuclear reactor core into a melt catcher. The technical result of the claimed invention is an increase in the effectiveness of confining and cooling the melt from the core of a nuclear reactor. The problem to be solved by the invention is the prevention of guiding device destruction due to shock concentration in the conical portion of the guiding device, which would result in the core, fragments of the internal structures and the bottom of the pressure vessel of the nuclear reactor simultaneously entering the melt catcher. According to the invention, a guiding device of a system for confining and cooling melt, which is installed below a reactor pressure vessel and is supported by a cantilever truss, comprises thermal elements in addition to a load-bearing frame, which in combination makes it possible to ensure that the core, fragments of the internal structures and the bottom of the pressure vessel of the nuclear reactor enter the melt catcher by excluding melting-through of the walls of the conical and cylindrical portions, and by redistributing flow streams of the core melt.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. The technical result of the claimed invention is an increase in the reliability of a system for confining and cooling melt from the core of a nuclear reactor, and an increase in the efficiency of heat removal from the melt from the core of a nuclear reactor. The technical result is achieved in that a system for confining and cooling melt from the core of a nuclear reactor includes a membrane, a drum and a thermal shield which are installed in the zone between a multilayer housing and a cantilever truss.

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 13/10 - Means for preventing contamination in event of leakage

Abstract

The invention relates to systems for confining and cooling the melt from the core of a nuclear reactor, which are intended to contain severe beyond design-basis accidents, more particularly devices for guiding the melt from the nuclear reactor core into a melt catcher. The technical result of the claimed invention is an increase in the effectiveness of confining and cooling the melt from the core of a nuclear reactor. The problem to be solved by the invention is the prevention of guiding device destruction due to shock concentration in the conical portion of the guiding device, which would result in the core, fragments of the internal structures and the bottom of the pressure vessel of the nuclear reactor simultaneously entering the melt catcher. According to the invention, a guiding device of a system for confining and cooling melt, which is installed below a reactor pressure vessel and is supported by a cantilever truss, comprises thermal elements in addition to a load-bearing frame, which in combination makes it possible to ensure that the core, fragments of the internal structures and the bottom of the pressure vessel of the nuclear reactor enter the melt catcher by excluding melting-through of the walls of the conical and cylindrical portions, and by redistributing flow streams of the core melt.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. The technical result of the claimed invention is an increase in the reliability of a system for confining and cooling melt from the core of a nuclear reactor, and an increase in the efficiency of heat removal from the melt from the core of a nuclear reactor. The technical result is achieved in that a system for confining and cooling melt from the core of a nuclear reactor includes a membrane, a drum and a thermal shield which are installed in the zone between a multilayer housing and a cantilever truss.

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 13/10 - Means for preventing contamination in event of leakage

Abstract

The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. The technical result of the claimed invention is an increase in the reliability of a system for confining and cooling melt from the core of a nuclear reactor, and an increase in the efficiency of heat removal from the melt from the core of a nuclear reactor. The technical result is achieved in that a system for confining and cooling melt from the core of a nuclear reactor includes a top thermal shield mounted in the zone between a housing and a cantilever truss, and a bottom thermal shield mounted inside the housing on an upper filler cassette.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. The technical result of the claimed invention is an increase in the reliability of a system for confining and cooling melt from the core of a nuclear reactor, and an increase in the efficiency of heat removal from the melt from the core of a nuclear reactor. The technical result is achieved in that a system for confining and cooling melt from the core of a nuclear reactor includes a membrane and a thermal shield which are installed in the zone between a multilayer housing and a cantilever truss.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPPs), and can be used in severe accidents resulting in molten core, destruction of the reactor vessel and molten metal output into the containment volume of NPP. The technical result of the claimed invention is to increase the reliability of the reactor molten core localization device. The technical result of reactor molten core localization device is achieved due to the lower support consisting of radial supports of a horizontal embedded slab and radial supports installed in the lower part of the molten metal trap casing joined together by clamps, while the radial supports and the fasteners have oval shaped openings.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. The technical result of the claimed invention is an increase in the reliability of a system for confining and cooling melt from the core of a nuclear reactor, and an increase in the efficiency of heat removal from the melt from the core of a nuclear reactor. The technical result is achieved in that a system for confining and cooling melt from the core of a nuclear reactor includes a top thermal shield mounted in the zone between a housing and a cantilever truss, and a bottom thermal shield mounted inside the housing on an upper filler cassette.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. The technical result of the claimed invention is an increase in the reliability of a system for confining and cooling melt from the core of a nuclear reactor, and an increase in the efficiency of heat removal from the melt from the core of a nuclear reactor. The technical result is achieved in that a system for confining and cooling melt from the core of a nuclear reactor includes a membrane and a thermal shield which are installed in the zone between a multilayer housing and a cantilever truss.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to a guide device for a system for confining and cooling nuclear reactor core melt in the event of severe beyond-design-basis accidents. The guide device, which is installed beneath a reactor vessel and rests on a cantilever truss, comprises a cylindrical portion and a conical portion with an opening therein, the walls of said portions being coated with a heat-resistant and low-melting material and being divided into sectors by reinforcing ribs arranged radially relative to the opening. A reinforcing framework of the guide device consists of an outer upper reinforcing ring, an outer lower reinforcing ring, an inner reinforcing shell, an outer upper reinforcing shell, a middle reinforcing shell divided into sectors by reinforcing ribs, and an outer lower reinforcing shell, as well as supporting ribs, a base, an upper inclined plate connecting the conical bottom, the reinforcing ribs and the middle reinforcing shell, and a lower inclined plate connecting the conical bottom, the reinforcing ribs and the outer upper reinforcing shell. The technical result consists in more effectively confining and cooling nuclear reactor core melt.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to a guide device for a system for confining and cooling nuclear reactor core melt in the event of severe beyond-design-basis accidents. The guide device, which is installed beneath a reactor vessel and rests on a cantilever truss, comprises a cylindrical portion and a conical portion with an opening therein, the walls of said portions being coated with a heat-resistant and low-melting material and being divided into sectors by reinforcing ribs arranged radially relative to the opening. A reinforcing framework of the guide device consists of an outer upper reinforcing ring, an outer lower reinforcing ring, an inner reinforcing shell, an outer upper reinforcing shell, a middle reinforcing shell divided into sectors by reinforcing ribs, and an outer lower reinforcing shell, as well as supporting ribs, a base, an upper inclined plate connecting the conical bottom, the reinforcing ribs and the middle reinforcing shell, and a lower inclined plate connecting the conical bottom, the reinforcing ribs and the outer upper reinforcing shell. The technical result consists in more effectively confining and cooling nuclear reactor core melt.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

This invention involves systems which provide for the safety of nuclear power plants that can be used in the event of serious accidents leading to the destruction of the housing and sealed containment structure of a reactor. In one aspect, the system can increase nuclear power plant safety by preventing the escape of liquid and solid radioactive materials (corium) from a melt confinement device in the event of a serious accident involving the escape of core melt from a nuclear reactor. The invention addresses the problem of increasing the efficiency and reliability of a melt confinement device by improving the conditions for cooling corium. The problem is solved by the use of a filler formed in upper cassettes and in a lower cassette. Said cassettes are configured with vertical and horizontal channels which provide for the uniform distribution of melt in the housing undergoing cooling.

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 13/10 - Means for preventing contamination in event of leakage
• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat

Abstract

A device for confining nuclear reactor core melt comprising a melt trap and provided with a multilayer vessel containment, a filler, an upper support, and a bottom support comprising a horizontal embedded plate mounted in the concrete of a reactor pit. The plate comprises radial supports, the melt trap comprising radial supports, based on the radial support of the plate. The plate radial supports and the melt trap radial supports are connected with fasteners having holes in the form of hyperbolic surfaces. The radial supports and the clamps have oval holes. The upper support comprises turnbuckles, mounted in pairs on the upper part of the melt trap body so that the longitudinal axis of each radial support of the melt trap bottom support passes in projection at an equispaced distance from the fitting location of the paired turnbuckles and connecting the melt trap body with the reactor pit vertical wall.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

System for confining and cooling melt from the core of a water-moderated nuclear reactor comprising a melt trap. The melt trap is installed in the reactor vessel bottom and provided with a cooled containment, consisting of outer and inner housings between which there is a sealant, and the filler for the melt dilution placed in the melt trap inner body. The melt trap inner body has a damper consisting of a central mantle, bearing ribs connected with the central mantle, titled plates, placed between the bearing ribs, the stops providing fastening of the damper to the melt trap body.

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat

Abstract

The steam generating unit of dual circuit reactor with blowdown and drain system is implemented in the close loop, without any conventional blowdown expansion tanks and is designed for maximum pressure of the steam generator (SG) working medium. The SG blowdown water is combined into a single line, cooled down in the regenerative heat exchanger, then in the blowdown aftercooler and drain cooling line and taken out of the tight shell. Out of the tight shell, the SG blowdown water is supplied for treatment to the SG blowdown water treatment system designed for maximum pressure of the steam generator (SG) working medium. After treatment, the water returns to the tight shell and, via the regenerative heat exchanger, to the feed pipelines of each SG. The invention provides increased SG blowdown that leads to the accelerated chemical condition normalization even with considerable deviations.

IPC Classes  ?

• F22B 37/52 - Washing-out devices
• F22B 35/00 - Control systems for steam boilers
• F22B 37/48 - Devices or arrangements for removing water, minerals or sludge from boilers
• F28G 9/00 - Cleaning by flushing or washing, e.g. with chemical solvents
• G21C 19/28 - Arrangements for introducing fluent material into the reactor coreArrangements for removing fluent material from the reactor core
• G21D 1/00 - Details of nuclear power plant

Abstract

The invention relates to structural engineering, and more particularly to reinforced concrete safety enclosures for nuclear power stations. The technical result of the claimed invention lies in increasing the safety of a nuclear power station, simplifying the structure of a reinforced concrete safety enclosure for a nuclear power station, and reducing the physical dimensions and installation time of a nuclear power station. The technical result is achieved by positioning an expanded steel sheet inside a concrete block such as to lie between longitudinal reinforcing bars and the rear side of a reinforced concrete safety enclosure, said expanded steel sheet having diamond-shaped cells configured therein, which are formed by inclined load-bearing ribs fastened to end supports of the reinforced concrete safety enclosure by a welded connection. Using an expanded steel sheet with diamond-shaped cells in a reinforced concrete safety enclosure of reduced thickness makes it possible to prevent pieces of concrete from getting inside a nuclear power station. Furthermore, since there is no need to increase the thickness of the safety enclosure, this both simplifies the structure and reduces the installation time of a nuclear power station.

IPC Classes  ?

• G21C 13/093 - Concrete vessels
• E04B 5/43 - Floor structures of extraordinary designFeatures relating to the elastic stabilityFloor structures specially designed for resting on columns only, e.g. mushroom floors
• E04H 5/02 - Buildings or groups of buildings for industrial purposes, e.g. for power-plants or factories

Abstract

Single-loop nuclear power plant with a pressurized coolant, comprising a power generating unit and a throttling device having an impeller, which are interconnected by an outlet pipe and a feed pipe, and a steam turbine connected to the throttling device and to a condenser connected to the throttling device, vertically divided into a steam zone, a high pressure zone, and a low pressure zone by horizontal partitions. The high pressure zone is connected to the the feed pipe and is connected to the low pressure zone by throttling nozzles provided in the partition between said zones, and the low pressure zone is connected to the steam zone by a vertical pipe which passes through the horizontal sealed partitions and the high pressure zone. The single-loop nuclear power plant is provided with an electric motor to rotate the impeller.

IPC Classes  ?

• G21C 1/08 - Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor
• G21C 15/243 - Promoting flow of the coolant for liquids
• G21D 1/00 - Details of nuclear power plant

Abstract

A condensation system for recuperating energy discharge of a nuclear power plant comprises a nuclear power unit, a compressor, a condenser, a water chamber equipped with a sprinkler, an electrical current generator, a pure water pump station, a cooling water pump station, a secondary condensate pool and a turboexpander. The compressor is connected to the condenser, which is connected to the turboexpander, which is supplied with the electric current generator and is connected to the water chamber, which is connected to the secondary condensate pool, which is connected to the pure water pump station, the condenser being connected to the cooling water pump station, wherein the compressor is connected by a pressure air duct to a wastewater channel, which is connected to the nuclear power unit and is equipped with a sealing cover.

IPC Classes  ?

• G21D 1/02 - Arrangements of auxiliary equipment
• G21D 1/04 - Pumping arrangements
• E03B 3/28 - Methods or installations for obtaining or collecting drinking water or tap water from humid air

Abstract

The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to reactor pressure vessel and its containment destruction.The technical result of the claimed invention is to increase the safety of a nuclear power plant by excluding the release of liquid and solid radioactive materials (corium) outside the device for confining core melt in the event of a severe accident with the core melt discharge out of the nuclear reactor.The object of the current invention is to improve the efficiency and reliability of the the device for confining core melt by improving the corium cooling conditions.The set object is solved based on the use of the filler formed in the cassettes, the upper and the lower ones. The cassettes have vertical and horizontal channels that ensure uniform distribution of the melt in the cooled body.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the housing and sealed containment structure of a reactor. The technical result of the claimed invention is to increase nuclear power plant safety by preventing the escape of liquid and solid radioactive materials (corium) from a melt confinement device in the event of a serious accident involving the escape of core melt from a nuclear reactor. The invention addresses the problem of increasing the efficiency and reliability of a melt confinement device by improving the conditions for cooling corium. The problem is solved by the use of a filler formed in upper cartridges and in a lower cartridge. Said cartridges are configured with vertical and horizontal channels which provide for the uniform distribution of melt in the housing undergoing cooling.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The group of inventions relates to systems for the safe operation of nuclear power stations in the event of an emergency. A method for cooling nuclear reactor core melt consists in determining the location of molten core fragments within a reactor vessel and the status of core penetration on the basis of information obtained from temperature sensors mounted inside the nuclear reactor, supplying a coolant to the reactor core, and increasing or reducing the volume of coolant supplied to the core after penetration of the reactor vessel. The degree of damage to the reactor vessel and the time of commencement of melt efflux from the vessel into a core catcher are determined. Coolant is supplied to the housing of the core catcher with a predetermined time delay. The time of commencement of crust formation, the time of cessation of aerosol release, the time of completion of vapour sorption, and the time of hydrogen formation are determined. The volume of coolant supplied is regulated taking into account the thermophysical properties of certain media, and the volume of coolant supplied is regulated taking into account minimum and maximum water levels in the reactor cavity. A system for monitoring the cooling of nuclear reactor core melt is also provided. The result is more efficient cooling of nuclear reactor core melt.

IPC Classes  ?

• G21C 15/18 - Emergency cooling arrangementsRemoving shut-down heat
• G21C 17/022 - Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators

Abstract

The invention relates to safe operation support systems of nuclear power plants (NPPs) at severe accidents, in particular, to methods and systems for cooling and cooling control of the reactors molten core.The technical result of the claimed inventions is to increase the safety of NPP, cooling efficiency of the molten core of a reactor.The objective of the claimed inventions is to increase the efficiency of cooling the molten core of a reactor by safely removing the heat load from the molten metal mirror, ensuring the elimination of vapour explosions leading to the destruction of the localization area of accidents, the reactor cavity and the containment.The technical result is achieved by changing the principle of cooling the reactor molten core, which consists in the fact that after the molten core destroys the reactor vessel, the conditions for subsequent cooling of the molten metal are determined by the characteristics of the trap casing, but not of the reactor.Besides, the technical result is achieved due to the installation of temperature sensors and level gauges designed to monitor the cooling process of the molten core of a reactor.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

A device for confining nuclear reactor core melt comprises a melt trap mounted beneath the bottom of a reactor housing and provided with a cooled shell in the form of a multi-layered housing, a filler for diluting the melt, said filler being disposed inside the multi-layered housing, an upper support, a lower support consisting of a horizontal segmented, continuous or split embedded plate mounted beneath the multi-layered housing in the concrete of a reactor shaft. The plate has radial supports, and the melt trap has radial supports resting against the radial supports of the plate. The radial supports of the melt trap housing are connected by fastening members. The radial supports and the fastening members have oval apertures, and the upper support comprises turnbuckles mounted in pairs in the upper part of the melt trap housing. The fastenings of the turnbuckles have apertures in the form of hyperbolic surfaces.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

A device for confining nuclear reactor core melt comprises a melt trap mounted beneath the bottom of a reactor housing and provided with a cooled shell in the form of a multi-layered housing, a filler for diluting the melt, said filler being disposed inside the multi-layered housing, an upper support, a lower support consisting of a horizontal segmented, continuous or split embedded plate mounted beneath the multi-layered housing in the concrete of a reactor shaft. The plate has radial supports, and the melt trap has radial supports resting against the radial supports of the plate. The radial supports of the melt trap housing are connected by fastening members. The radial supports and the fastening members have oval apertures, and the upper support comprises turnbuckles mounted in pairs in the upper part of the melt trap housing. The fastenings of the turnbuckles have apertures in the form of hyperbolic surfaces.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to core meltdown, destruction of the reactor housing and the escape of melt into the sealed containment structure of a nuclear power plant. The technical result of the claimed invention is an increase in the reliability of a device for confining nuclear reactor core melt. This technical result is achieved by using a lower support in a device for confining nuclear reactor core melt, said lower support consisting of radial supports of a horizontal embedded plate, and radial supports mounted in the bottom part of the housing of a melt trap, said supports being connected to one another by fastening members, wherein the radial supports and the fastening members have oval apertures.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPPs), and can be used in severe accidents resulting in molten core, destruction of the reactor vessel and molten metal output into the containment volume of NPP.The technical result of the claimed invention is to increase the reliability of the reactor molten core localization device.The technical result of reactor molten core localization device is achieved due to the lower support consisting of radial supports of a horizontal embedded slab and radial supports installed in the lower part of the molten metal trap casing joined together by clamps, while the radial supports and the fasteners have oval shaped openings.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of atomic energy, specifically to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the meltdown of the core, to the destruction of a nuclear reactor housing and to the discharge of melt into the region of a hermetic containment structure of a nuclear power plant. The technical result is an increase in the reliability of a system for confining and cooling melt from the core of a water-moderated nuclear reactor. The problem addressed by the present invention is that of increasing the efficiency of removing heat from the melt and of increasing the reliability of a structure. The stated problem is solved by the use, in a system for confining and cooling melt from the core of a water-moderated nuclear reactor, of a damper which is installed inside a melt trap housing.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to the field of pipelines and equipment and can be used in various technical fields: at nuclear power plant facilities, in heat engineering, in mechanical engineering, in petrochemistry, in water supply, in the chemical industry, in the aerospace industry and in other technical fields. The present group of inventions addresses the problem of creating a thermal insulation jacket for pipes which consists of metallic elements, and a method for the installation thereof that provides reliable electrical insulation of the elements from one another. This problem is solved in that the metallic elements are connected with an overlap, and the elements are provided in the overlap region with openings in which electrically insulating gaskets are affixed which are made of resilient, elastoplastic, plastic, or fully or partially thermoset material providing electrical insulation between adjacent elements. When the jacket is installed, material of the electrically insulating gaskets is applied to the overlap regions of the metallic elements such that, during installation compression of each successive metallic element, the material of the electrically insulating gaskets fills the openings of the overlap regions of the metallic elements so as to form reliable pin connections between a gasket and adjacent elements of the jacket. The numerous pin connections obtained provide fixation of adjacent metallic elements without impairing their electrical insulation from one another.

IPC Classes  ?

• F16L 59/10 - Bandages or covers for the protection of the insulation, e.g. against the influence of the environment or against mechanical damage
• F16L 59/00 - Thermal insulation in general

Abstract

The invention relates to the field of atomic energy, specifically to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the meltdown of the core, to the destruction of a nuclear reactor housing and to the discharge of melt into the region of a hermetic containment structure of a nuclear power plant. The technical result is an increase in the reliability of a system for confining and cooling melt from the core of a water-moderated nuclear reactor. The problem addressed by the present invention is that of increasing the efficiency of removing heat from the melt and of increasing the reliability of a structure. The stated problem is solved by the use, in a system for confining and cooling melt from the core of a water-moderated nuclear reactor, of a damper which is installed inside a melt trap housing.

IPC Classes  ?

• G21C 9/016 - Core catchers

Abstract

The invention relates to pipelines and equipment and shall be used in different fields of the invention: at nuclear power plants, in heat power engineering, manufacturing engineering, petrochemistry, water supply, chemical and aerospace industries as well as other fields.The invention group is designed for development of a pipe heat insulation casing consisted of metal elements and assembly method ensuring reliable electrical insulation of all elements.The set object is resolved by that the connection of the metal elements is with lapping, the elements are with openings in the lapping area where the electrically-insulating spacers are set made of resilient, elastic-plastic, plastic, fully viscous or partially solidified material ensuring electrical insulation between the adjacent elements. At assembly of the casing the material of the electrically-insulating spacers is applied to the lapping areas of the metal elements in such a way to flll the openings of the lapping areas of the metal elements by the material of the electrically-insulating spacers in case of assembly compression of each next metal element thus arranging reliable pin connections between the spacer and adjacent casing elements. Multiple pin connections ensure fixation of the adjacent metal elements without any failure to electrical insulation of each other.2 independent claims documents, 13 dependent clams documents, 4 figures.

IPC Classes  ?

• F16L 59/14 - Arrangements for the insulation of pipes or pipe systems

Abstract

The invention relates to atomic energy, more particularly to systems for recuperating energy discharge of nuclear power plants and is aimed at providing high productivity of the process of obtaining fresh water by recuperating thermal energy of water of a discharge channel of a nuclear power plant by recycling the wet high-temperature vapor thereof, as well as at raising the use factor of heat from nuclear power plants and reducing the adverse effect of waste water on the environment. A condensation system for recuperating energy discharge of a nuclear power plant comprises a nuclear power unit, an air intake means, a compressor, a condenser, a water chamber equipped with a sprinkler, an electrical current generator, a pure water pump station, a cooling water pump station, a secondary condensate pool and a turboexpander. The air intake means is connected to a compressor, which is connected to the condenser, which is connected to the turboexpander, which is supplied by the electric current generator and is connected to the water chamber, which is connected to the secondary condensate pool, which is connected to the pure water pump station, the condenser being connected to the cooling water pump station, wherein the air intake means is accommodated in the discharge water channel, which is connected to the nuclear power unit and is equipped with a sealing cover.

IPC Classes  ?

• B01D 5/00 - Condensation of vapoursRecovering volatile solvents by condensation
• E03B 3/28 - Methods or installations for obtaining or collecting drinking water or tap water from humid air
• G21D 1/02 - Arrangements of auxiliary equipment

Abstract

The proposed double-loop nuclear reactor steam generating plant having a blowdown and drainage system is implemented on the basis of a closed loop without the conventional blowdown tanks and is designed for maximum pressure of the working fluid in the steam generators. Steam generator blowdown water is brought together into a single line, cooled in a regenerative heat exchanger then in a blowdown and drainage aftercooler, and removed from the containment building. Outside the containment building, the steam generator blowdown water is fed for treatment into a system for the specialized treatment of steam generator blowdown water, designed for maximum pressure of the working fluid in the steam generators. After treatment, the blowdown water is returned to the containment building and, via the regenerative heat exchanger, to feed pipes of each steam generator. The technical result is an increase in steam generator blowdown flow, which leads to the accelerated normalization of the water chemistry conditions even in the event of significant deviations and, as a result, to an increase in the working life of each steam generator and of the steam generating plant as a whole, and also leads to a reduction in energy losses during the return of the treated blowdown water to the second loop, while at the same time rendering the system autonomous due to the absence of a link to turbine hall equipment.

IPC Classes  ?

• F22B 37/52 - Washing-out devices
• F28G 9/00 - Cleaning by flushing or washing, e.g. with chemical solvents
• G21C 1/00 - Reactor types

Abstract

The proposed double-loop nuclear reactor steam generating plant having a blowdown and drainage system is implemented on the basis of a closed loop without the conventional blowdown tanks and is designed for maximum pressure of the working fluid in the steam generators. Steam generator blowdown water is brought together into a single line, cooled in a regenerative heat exchanger then in a blowdown and drainage aftercooler, and removed from the containment building. Outside the containment building, the steam generator blowdown water is fed for treatment into a system for the specialized treatment of steam generator blowdown water, designed for maximum pressure of the working fluid in the steam generators. After treatment, the blowdown water is returned to the containment building and, via the regenerative heat exchanger, to feed pipes of each steam generator. The technical result is an increase in steam generator blowdown flow, which leads to the accelerated normalization of the water chemistry conditions even in the event of significant deviations and, as a result, to an increase in the working life of each steam generator and of the steam generating plant as a whole, and also leads to a reduction in energy losses during the return of the treated blowdown water to the second loop, while at the same time rendering the system autonomous due to the absence of a link to turbine hall equipment.

IPC Classes  ?

• F22B 37/52 - Washing-out devices
• F22B 37/54 - De-sludging or blow-down devices
• F22D 11/00 - Feed-water supply not provided for in other main groups

Abstract

The invention relates to atomic energy, more particularly to systems for recuperating energy discharge of nuclear power plants and is aimed at providing high productivity of the process of obtaining fresh water by recuperating thermal energy of water of a discharge channel of a nuclear power plant by recycling the wet high-temperature vapor thereof, as well as at raising the use factor of heat from nuclear power plants and reducing the adverse effect of waste water on the environment. A condensation system for recuperating energy discharge of a nuclear power plant comprises a nuclear power unit, an air intake means, a compressor, a condenser, a water chamber equipped with a sprinkler, an electrical current generator, a pure water pump station, a cooling water pump station, a secondary condensate pool and a turboexpander. The air intake means is connected to a compressor, which is connected to the condenser, which is connected to the turboexpander, which is supplied by the electric current generator and is connected to the water chamber, which is connected to the secondary condensate pool, which is connected to the pure water pump station, the condenser being connected to the cooling water pump station, wherein the air intake means is accommodated in the discharge water channel, which is connected to the nuclear power unit and is equipped with a sealing cover.

IPC Classes  ?

• B01D 5/00 - Condensation of vapoursRecovering volatile solvents by condensation
• E03B 3/28 - Methods or installations for obtaining or collecting drinking water or tap water from humid air
• G21D 1/02 - Arrangements of auxiliary equipment

Abstract

A disposable emergency thermal valve comprises a body having a through channel for supplying coolant liquid through the inlet opening thereof in the direction of the outlet opening thereof, and a fuse arranged in the through channel of the body and consisting of at least two parts which fully cover the cross section of the through channel, are made of materials having different melting temperatures and which are arranged in the through channel successively with an increase in the melting temperature of each subsequent part in the direction from the inlet opening of the through channel to the outlet opening thereof, wherein the body can have transverse reinforcing ribs and/or transverse projections where the fuse is arranged.

IPC Classes  ?

• F16K 17/40 - Safety valvesEqualising valves with fracturing member, e.g. fracturing diaphragm, fusible joint

Abstract

AbstractThere is disclosed herein a single-action emergency thermal valve comprising a body with a through channel for coolant supply through an inlet of the channel in the direction of an outlet of the channel, and a fuse link in the through channel of the body, the fuse link comprising at least two parts that completely overlap a section of the through channel, wherein the parts are made of materials with different melting points, and are located in the through channel in series in increasing order of the melting points of each of the parts in a direction from the through channel inlet to its outlet.Date Recue/Date Received 2020-12-17

IPC Classes  ?

• F16K 17/00 - Safety valvesEqualising valves
• F16K 17/40 - Safety valvesEqualising valves with fracturing member, e.g. fracturing diaphragm, fusible joint

Abstract

In a single-loop nuclear power plant with a pressurized coolant, comprising a power generating unit and a throttling device having an impeller, which are interconnected by an outlet pipe and a feed pipe, and a steam turbine connected by pipes to the throttling device and to a condenser which is also connected to the throttling steam generator, the throttling device is configured in the form of a throttling steam generator which is vertically divided into a vapour zone, a high pressure zone, and a low pressure zone by means of horizontal sealed partitions, the vapour zone is situated above the high pressure zone, which is situated above the low pressure zone, the high pressure zone is connected to the inlet of the feed pipe and is connected to the low pressure zone by throttling nozzles provided in the partition between said zones, about the periphery of said partition and at an angle to the vertical, and the low pressure zone is connected to the vapour zone by a vertical pipe which passes through the centres of the horizontal sealed partitions and the high pressure zone, wherein the single-loop nuclear power plant is additionally provided with an electric motor configured for rotation of the impeller. The single-loop nuclear power plant with a pressurized coolant and a throttling steam generator allows highly efficient use of nuclear fuel, and also provides reliable and safe operation in all regimes, and is applicable in the nuclear power industry.

IPC Classes  ?

• G21D 1/00 - Details of nuclear power plant

Abstract

In a single-loop nuclear power plant with a pressurized coolant, comprising a power generating unit and a throttling device having an impeller, which are interconnected by an outlet pipe and a feed pipe, and a steam turbine connected by pipes to the throttling device and to a condenser which is also connected to the throttling steam generator, the throttling device is configured in the form of a throttling steam generator which is vertically divided into a vapour zone, a high pressure zone, and a low pressure zone by means of horizontal sealed partitions, the vapour zone is situated above the high pressure zone, which is situated above the low pressure zone, the high pressure zone is connected to the inlet of the feed pipe and is connected to the low pressure zone by throttling nozzles provided in the partition between said zones, about the periphery of said partition and at an angle to the vertical, and the low pressure zone is connected to the vapour zone by a vertical pipe which passes through the centres of the horizontal sealed partitions and the high pressure zone, wherein the single-loop nuclear power plant is additionally provided with an electric motor configured for rotation of the impeller. The single-loop nuclear power plant with a pressurized coolant and a throttling steam generator allows highly efficient use of nuclear fuel, and also provides reliable and safe operation in all regimes, and is applicable in the nuclear power industry.

IPC Classes  ?

• G21D 1/00 - Details of nuclear power plant

Abstract

The sphere of main pipelines used for hot water supply, specifically devices for electric surveillance control and water heat carrier leakage detection on atomic electric power station pipelines applied for operation of heat insulated pipes with a protective casing. Such pipeline leakage detection device uses a metal protective casing installed coaxially on a metal pipe with a radial clearance, where the casing performs as a joint of, for example, four arch shaped metal sheets bent across the pipe. Sheets straight line edges are joined by a dielectric washer, and sheets arch shaped edges are joined by a dielectric ring. Ring flanks have ring grooves on them for sheets arch shaped edges installation. Across each sheet arch shaped edge there are lamels shaped electric connectors installed in ring grooves for sheet arch shaped edge fixation. Electric connector terminals are fastened on the ring external surface and separately connected to each lamel.

IPC Classes  ?

• G01R 27/08 - Measuring resistance by measuring both voltage and current
• G01M 3/16 - Investigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using electric detection means
• F17D 5/04 - Preventing, monitoring, or locating loss by means of a signalling fluid enclosed in a double wall
• G01M 3/18 - Investigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using electric detection means for pipes, cables, or tubesInvestigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using electric detection means for pipe joints or sealsInvestigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using electric detection means for valves
• F16L 59/10 - Bandages or covers for the protection of the insulation, e.g. against the influence of the environment or against mechanical damage

Abstract

There is disclosed herein a pipeline leakage detection device with a metal protective casing installed coaxially on a metal pipe 2 with a radial clearance 1, where casing is performed as a joint of, for example, four arch shaped metal sheets 4 bent across the pipe 2. Sheets 4 straight line edges 7 are joined with one another by means of a dielectric washer 8, and sheets 4 arch shaped edges 9 are joined with one another by means of a dielectric ring 10. Ring 10 flanks 15 and 16 have ring grooves 17 and 18 on them for sheets 10 arch shaped edges 9 installation. Across each sheet 10 arch shaped edge 9 there are lamels shaped electric connectors 21 installed in ring grooves 17 and 18 for sheet 4 arch shaped edge 9 fixation. Electric connector terminals 30 are fastened on the ring 10 external surface 22 and are separately connected to each lamel 21.

IPC Classes  ?

• F17D 5/04 - Preventing, monitoring, or locating loss by means of a signalling fluid enclosed in a double wall
• G01M 3/16 - Investigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using electric detection means

Abstract

A device for detecting leaks of an aqueous heat transfer medium comprises a protective casing coaxially mounted on a metal pipe (2) such that an annular gap (1) is provided, said protective casing being comprised of four metal sheets (4) curved arcuately around the pipe (2). The straight edges of the sheets (4) are connected to one another by means of a dielectric pad, and the curved edges (9) of the sheets (4) are connected to one another by means of a dielectric ring (10). The faces (15) and (16) of the ring (10) are each provided with an annular groove (17) and (18) for accommodating the curved edges (9). Opposite each curved edge (9) in the annular grooves (17) and (18) there are mounted electrical connectors in the form of lamellae for securing the curved edge (9). Contact terminals (30) are fastened on the outside surface (22) of the ring (10) and are individually connected to each lamella. A measuring instrument (33) is connected by conductors (32) to a terminal (31) on the pipe (2) and to the contact terminals (30) on the ring (10) in order to determine the electrical resistance of thermal insulation (3) in the annular gap (1). The invention increases the accuracy with which the site of a leak is detected and simplifies the maintenance of thermally insulated pipelines.

IPC Classes  ?

• F17D 5/04 - Preventing, monitoring, or locating loss by means of a signalling fluid enclosed in a double wall
• G01M 3/16 - Investigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using electric detection means

Abstract

?The invention relates to the field of atomic energy, and specifically to systems which provide for the safety of nuclear power plants, and may be used in the event of serious accidents leading to the destruction of a reactor housing and of the hermetic containment structure of a nuclear power plant. A system for confining and cooling melt contains: a guide plate in the form of a funnel, installed under the bottom of a reactor housing; a cantilever truss, installed under the guide plate so that the plate rests on same; a melt catcher, installed under the cantilever truss and provided with a cooling casing in the form of a multi-layered vessel for protecting an outer heat-exchange wall against dynamic, thermal and chemical influences; and a filler for diluting the melt, located in said multi-layered vessel. Said multi-layered vessel contains a metal inner layer and a metal outer layer, between which is provided an intermediate layer in the form of a non-metal filler; wherein, reinforcing ribs are provided between the inner and outer layers, said ribs being installed with an azimuthal spacing (s???) which satisfies the condition: d???/15

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 13/10 - Means for preventing contamination in event of leakage

Abstract

?The invention relates to the field of atomic energy, and specifically to systems which provide for the safety of nuclear power plants, and may be used in the event of serious accidents leading to the destruction of a reactor housing and of the hermetic containment structure of a nuclear power plant. A system for confining and cooling melt contains: a guide plate in the form of a funnel, installed under the bottom of a reactor housing; a cantilever truss, installed under the guide plate so that the plate rests on same; a melt catcher, installed under the cantilever truss and provided with a cooling casing in the form of a multi-layered vessel for protecting an outer heat-exchange wall against dynamic, thermal and chemical influences; and a filler for diluting the melt, located in said multi-layered vessel. Said multi-layered vessel contains a metal outer wall and a metal inner wall, and, positioned between same, a filler made of a material which has low thermal conductivity relative to the materials of the walls. The thickness of the filler h??? satisfies the condition of: 0.8h???

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 13/10 - Means for preventing contamination in event of leakage

Abstract

?The invention relates to the field of atomic energy, and specifically to systems which provide for the safety of nuclear power plants, and may be used in the event of serious accidents leading to the destruction of a reactor housing and of the hermetic containment structure of a nuclear power plant. A system for confining and cooling melt contains: a guide plate in the form of a funnel, installed under the bottom of the reactor housing; a cantilever truss, installed under the guide plate so that the plate rests on same; a melt catcher, installed under the cantilever truss and provided with a cooling casing in the form of a multi-layered vessel for protecting an outer heat-exchange wall against dynamic, thermal and chemical influences; and a filler for diluting the melt, located in said multi-layered vessel. Said multi-layered vessel contains a metal outer wall and a metal inner wall, and, positioned between same, a filler made of a material which has high thermal conductivity relative to the materials of the walls; the thickness of the filler h??? satisfies the condition of: 1.2h???

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 13/10 - Means for preventing contamination in event of leakage

Abstract

The invention relates to the field of atomic energy, and specifically to systems which provide for the safety of nuclear power plants, and may be used in the event of serious accidents leading to the destruction of a reactor housing and of the hermetic containment structure of a nuclear power plant. A system for confining and cooling melt contains: a guide plate in the form of a funnel, installed under the bottom of a reactor housing; a cantilever truss, installed under the guide plate so that the plate rests on same; a melt catcher, installed under the cantilever truss and provided with a cooling casing in the form of a multi-layered vessel for protecting an outer heat-exchange wall against dynamic, thermal and chemical influences; and a filler for diluting the melt, located in said multi-layered vessel. Said multi-layered vessel contains a metal inner layer and a metal outer layer, between which is provided an intermediate layer in the form of a non-metal filler; wherein, reinforcing ribs are provided between the inner and outer layers, said ribs being installed with an azimuthal spacing (sшаг) which satisfies the condition: dнар/15

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 13/10 - Means for preventing contamination in event of leakage

Abstract

The invention relates to the field of atomic energy, and specifically to systems which provide for the safety of nuclear power plants, and may be used in the event of serious accidents leading to the destruction of a reactor housing and of the hermetic containment structure of a nuclear power plant. A system for confining and cooling melt contains: a guide plate in the form of a funnel, installed under the bottom of a reactor housing; a cantilever truss, installed under the guide plate so that the plate rests on same; a melt catcher, installed under the cantilever truss and provided with a cooling casing in the form of a multi-layered vessel for protecting an outer heat-exchange wall against dynamic, thermal and chemical influences; and a filler for diluting the melt, located in said multi-layered vessel. Said multi-layered vessel contains a metal outer wall and a metal inner wall, and, positioned between same, a filler made of a material which has low thermal conductivity relative to the materials of the walls. The thickness of the filler hзап satisfies the condition of: 0.8hнар

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 13/10 - Means for preventing contamination in event of leakage

Abstract

The invention relates to the field of atomic energy, and specifically to systems which provide for the safety of nuclear power plants, and may be used in the event of serious accidents leading to the destruction of a reactor housing and of the hermetic containment structure of a nuclear power plant. A system for confining and cooling melt contains: a guide plate in the form of a funnel, installed under the bottom of the reactor housing; a cantilever truss, installed under the guide plate so that the plate rests on same; a melt catcher, installed under the cantilever truss and provided with a cooling casing in the form of a multi-layered vessel for protecting an outer heat-exchange wall against dynamic, thermal and chemical influences; and a filler for diluting the melt, located in said multi-layered vessel. Said multi-layered vessel contains a metal outer wall and a metal inner wall, and, positioned between same, a filler made of a material which has high thermal conductivity relative to the materials of the walls; the thickness of the filler hзап satisfies the condition of: 1.2hнар

IPC Classes  ?

• G21C 9/016 - Core catchers
• G21C 13/10 - Means for preventing contamination in event of leakage

Abstract

?The invention relates to the field of electrical engineering, and specifically to sealed inlets of electrical circuits into a sealed area of a multi-layered containment shell of a nuclear power station. This design can be used in passages through an external and an internal wall which are subject to relative mutual displacement as a consequence of a seismic phenomenon or thermal expansion of the walls and passage. The problem addressed by the present invention is that of increasing the operating reliability of a sealed cable inlet when high-voltage electrical conductors which have little bending capacity are used. The problem addressed is achieved in that the sealed cable inlet through an external and an internal wall of a containment shell of a nuclear power station comprises an embedded pipe (3) which is arranged in the internal wall (1), with an inlet section (44) of a cable (2) fixed rigidly within said pipe. A means for compensating for a relative movement between the cable (2) and the external wall (11) is mounted in the external wall (11) coaxially with respect to the pipe (3). The compensating means has a tube (19) with a bellows (24) on the external end plane (20) and with a second analogous bellows (25) which is mounted symmetrically on the opposite end plane (21) of the tube (19) at the internal surface (18) of the external wall (11). The free ends (30) and (31) of the two bellows (24) and (25) are of conical design and have internal surfaces (28) and (29) which are support elements for an outlet section (46) of the cable (2), which is arranged freely in the tube (19) with a gap (47) relative to the internal surface (49) of the tube (19). The gap (47) between the braiding (48) along the external surface of the cable (2) and the internal surface (49) of the tube (19) is selected using a design calculation. The gap (47) must not be less than the value of maximum orthogonal thermo-seismic movement in one plane of the internal wall (1) relative to the external wall (11) and change in the coaxial position of the cable (2) in the tube (19).

IPC Classes  ?

• G21C 13/04 - Arrangements for expansion and contraction
• H02G 3/22 - Installations of cables or lines through walls, floors or ceilings, e.g. into buildings

Abstract

The invention relates to the field of electrical engineering, and specifically to sealed inlets of electrical circuits into a sealed area of a multi-layered containment shell of a nuclear power station. This design can be used in passages through an external and an internal wall which are subject to relative mutual displacement as a consequence of a seismic phenomenon or thermal expansion of the walls and passage. The problem addressed by the present invention is that of increasing the operating reliability of a sealed cable inlet when high-voltage electrical conductors which have little bending capacity are used. The problem addressed is achieved in that the sealed cable inlet through an external and an internal wall of a containment shell of a nuclear power station comprises an embedded pipe (3) which is arranged in the internal wall (1), with an inlet section (44) of a cable (2) fixed rigidly within said pipe. A means for compensating for a relative movement between the cable (2) and the external wall (11) is mounted in the external wall (11) coaxially with respect to the pipe (3). The compensating means has a tube (19) with a bellows (24) on the external end plane (20) and with a second analogous bellows (25) which is mounted symmetrically on the opposite end plane (21) of the tube (19) at the internal surface (18) of the external wall (11). The free ends (30) and (31) of the two bellows (24) and (25) are of conical design and have internal surfaces (28) and (29) which are support elements for an outlet section (46) of the cable (2), which is arranged freely in the tube (19) with a gap (47) relative to the internal surface (49) of the tube (19). The gap (47) between the braiding (48) along the external surface of the cable (2) and the internal surface (49) of the tube (19) is selected using a design calculation. The gap (47) must not be less than the value of maximum orthogonal thermo-seismic movement in one plane of the internal wall (1) relative to the external wall (11) and change in the coaxial position of the cable (2) in the tube (19).

IPC Classes  ?

• G21C 13/04 - Arrangements for expansion and contraction
• H02G 3/22 - Installations of cables or lines through walls, floors or ceilings, e.g. into buildings