WO2021047697A1 - Long-term heat removal system from a containment - Google Patents

Long-term heat removal system from a containment Download PDF

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Publication number
WO2021047697A1
WO2021047697A1 PCT/CZ2020/050062 CZ2020050062W WO2021047697A1 WO 2021047697 A1 WO2021047697 A1 WO 2021047697A1 CZ 2020050062 W CZ2020050062 W CZ 2020050062W WO 2021047697 A1 WO2021047697 A1 WO 2021047697A1
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WO
WIPO (PCT)
Prior art keywords
circuit
hot
cold
cooling medium
containment
Prior art date
Application number
PCT/CZ2020/050062
Other languages
French (fr)
Inventor
Jiri SOUKAL
Zdenek TUMA
Josef VECERA
Tomas KRATKY
Original Assignee
Centrum Hydraulickeho Vyzkumu Spol. S R.O.
Cez, A.S.
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Centrum Hydraulickeho Vyzkumu Spol. S R.O., Cez, A.S. filed Critical Centrum Hydraulickeho Vyzkumu Spol. S R.O.
Priority to HU2200126A priority Critical patent/HUP2200126A1/en
Priority to FI20225195A priority patent/FI130325B/en
Publication of WO2021047697A1 publication Critical patent/WO2021047697A1/en

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/02—Arrangements of auxiliary equipment
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention concerns a long-term heat removal system from a containment.
  • the present regulations require such arrangement performed by provider of the nuclear power plant, which are able to predict or reduce effect of the serious accident of a nuclear power plant, which are more difficult to be solved by standardized emergency tools.
  • a set of arrangements was defined.
  • One of them is to create a new functionally and energetically autonomous system for longterm heat transfer from a containment.
  • the requirement for performance of such system is, that a containment of a reactor effected by serious accident has to be cooled by water brought from outside, which flows into a shaft of the reactor from a pool performed on a floor of the containment. Heated water evaporates and escapes in form of vapor to the containment, by which it is pressured and the construction of it is heated. If such situation is not solved, risk of rupture of integrity of the containment by the higher pressure, which is above secure limit of the construction, may occur. It is necessary to avert pressurization of such space under the defined secure limit and stabilize pressure in the containment at low limit.
  • a long-term heat removal system is presented in a document EP 3451 346 A1.
  • the system comprises a cold circuit and a hot circuit, where a cold circuit comprises a pump station connected by its one end to a source of cooling medium of the cold circuit and by its second end to a turbine, from which the cooling liquid is led through a cold circuit of a cooler back to the source of the cooling medium of the cold circuit.
  • the hot circuit comprises a pump of a heat circuit connected by its input to a source of a cooling medium of the heat circuit, specifically a floor of the containment, and by its output to the hot circuit of the cooler, from which the cooling medium is led to a shower.
  • a disadvantage of such solution is, that in case, when the temperature of the cooling medium on the bottom of the containment reaches its boiling point, pumping of it is very difficult, because not only liquid is transported but also gas, which influences quality of interchange in the heat exchanger.
  • the aim of the invention is to present a long-term heat removal system from a containment, which is able to eliminate the above mentioned disadvantages.
  • a long-term heat removal system from containment comprises a cold circuit and a hot circuit
  • the cold circuit comprises a feed pump station on its one side connected to a source of cooling medium of the cold circuit and by its second side to a small impurity filter, which is connected to a main pump station, which is connected by inlet closing valve to a turbine, and then by cold circuit of a cooler and an outlet closing valve to the source of cooling medium of the cold circuit
  • the hot circuit comprises a pump of the hot circuit connected on its outlet by a hot circuit of the cooler to a shower arranged in the containment, and on inlet by a mechanical strainer to a source of cooling medium of the hot circuit, where the main pump station is connected by a primary extra cooling branch of the heat circuit to the inlet of the pump of the hot circuit, by which the cooling medium of the cold circuit is mixed with the cooling medium of the hot circuit.
  • the cold circuit comprises a primary extra cooling branch of the cold circuit, which connects the inlet of the small impurity filter with the source of cooling medium of the cold circuit and/or the secondary extra cooling branch of the cold circuit, which connects the outlet of the main pump station with the source of cooling medium of the cold circuit.
  • the hot circuit comprises a secondary extra cooling branch of the hot circuit, which connects the outlet of the hot circuit of the cooler with the inlet of the pump.
  • the long-term heat removal system from a containment according to the invention presented in Fig. 1, comprises a cold circuit and a hot circuit.
  • the cold circuit comprises a feed pump station 1 on its one side connected to a source of cooling medium of the cold circuit and by its second side to a small impurity filter 2, which is connected to a main pump station 3, which is connected by inlet closing valve 4 to a turbine 5, and then by cold circuit of a cooler 6 and an outlet closing valve 7 to the source of cooling medium of the cold circuit, by which the cold circuit is closed.
  • the hot circuit comprises a pump 8 of the hot circuit connected on its outlet by a hot circuit of the cooler 6 to a shower 9 arranged in the containment 10, and on inlet by a mechanical strainer 11 to a source of cooling medium of the hot circuit.
  • the main pump station 3 is connected by a primary extra cooling branch 19a of the heat circuit, which comprises a closing valve 20a, to the inlet of the pump 8 of the hot circuit, by which additional cooling of the cooling medium of the hot circuit floating to the pump 8 is performed, to ensure its correct function.
  • the source of the cooling medium of the cold circuit is a pool 12 of a cooling tower 13.
  • the cooling medium is for example water.
  • the cold circuit is provided by desedimentation branch 14, which connects the small impurity filter 2 with a desedimentation tank 15. If it is noticed by sensors arranged in the filter 2, that the filter is clogged, its washout is performed and sediments are flushed into the desedimentation tank 15.
  • the desedimentation branch 14 is provided by desedimentation valve 16.
  • the cold circuit is provided by one or two extra cooling branches 17a and 17b of the cold circuit.
  • the primary extra cooling branch 17a of the cold circuit connects the inlet of the small impurity filter 2 with the source of cooling medium of the cold circuit.
  • the secondary extra cooling branch 17b of the cold circuit connects the outlet of the main pump station 3 with the source of cooling medium of the cold circuit.
  • Both of those branches 17a, 17b of the cold circuit are possibly activated by regulation valves 18a, 18b, when temperature of the cooling medium of the cold circuit takes over predetermined limit.
  • the source of the cooling medium of the hot circuit is the bottom part of the containment 10, which is filled by the shower 9.
  • the cooling medium comprises a mixture of water and boron acid.
  • the turbine 5 and the pump 8 form one compact aggregate with single rotor system, i.e. a turbopump.
  • the hot circuit is advantageously provided with a secondary extra cooling branch 19b of the hot circuit, which comprises a closing valve 20b, which connects the outlet of the hot circuit of the cooler 6 with the inlet of the pump 8. Because of that, limited capacity of the cooling medium in the containment 10 is solved, which should be insufficient for long-term heat transfer. If the extra cooling branch is missing, a critical temperature should be reached in few hours.
  • the feed pump station 1 takes cold water from the pool 12 under the cooling tower 13 of a power plant, respectively from the reservoirs of fan cooling towers 13, and transports it through the impurity filter 2, which is intended for ensuring quality of the water, to the main pump station 3,
  • Both pump stations 1 and 3 comprise pump aggregates with a thermic diesel actuator. Pressurized water is than led from the main pump station 3 to the inlet of the containment 10 of the reactor block.
  • the pump 8 of the hot circuit sucks the hot mixture of water and boron acid from the bottom of the containment 10, filtrates it through the mechanical screen 11 and leads it to the hot circuit of the hot exchanger, respectively the cooler 6, and then to the dropping system, specifically the shower 9, arranged inside the containment 10, where it ensures required cooling effect of imoortant comoonents of the containment 10 of the reactor.
  • the long-term heat removal system according to the invention is fully autonomous, independent to technology of used devices of the nuclear reactor, and to an external power source, specifically a source of electricity. Possible exceptions should be components of the system, which are placed out of the containment and freely accessible even in time of serious accident, even though for a limited time, for example for the time required for refilling of fuel Into a thermic engine, etc.
  • the long-term heat removal system from a containment according to the invention is intended for nuclear power plants with a light water reactor of a WER type

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Separation Using Semi-Permeable Membranes (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Motor Or Generator Cooling System (AREA)

Abstract

Long-term heat removal system from containment comprises a cold circuit and a hot circuit, where the cold circuit comprises a feed pump station (1) on its one side connected to a source of cooling medium of the cold circuit and by its second side to a small impurity filter (2), which is connected to a main pump station (3), which is connected by inlet closing valve (4) to a turbine (5), and then by cold circuit of a cooler (6) and an outlet closing valve (7) to the source of cooling medium of the cold circuit, the hot circuit comprises a pump (8) of the hot circuit connected on its outlet by a hot circuit of the cooler (6) to a shower (9) arranged in the containment (10), and on inlet by a mechanical strainer (11) to a source of cooling medium of the hot circuit, where the main pump station (3) is connected by a primary extra cooling branch (19a) of the heat circuit to the inlet of the pump (8) of the hot circuit, by which the cooling medium of the cold circuit is mixed with the cooling medium of the hot circuit.

Description

Long-term heat removal system from a containment
Background of the Invention
[001] The present invention concerns a long-term heat removal system from a containment.
State of the art
[002] Effort to improve safety of nuclear power plants and experience about nuclear accidents in past go towards performance of sophisticated topology of failures and breakdowns, which are defined as predictable and standardized. There exist systems for solving those small impact incidents, which are implemented into technological devices of the power plants at the beginning of preparation of the nuclear power plant project.
[003] The present regulations require such arrangement performed by provider of the nuclear power plant, which are able to predict or reduce effect of the serious accident of a nuclear power plant, which are more difficult to be solved by standardized emergency tools. In case of serious incidents a set of arrangements was defined. One of them is to create a new functionally and energetically autonomous system for longterm heat transfer from a containment. The requirement for performance of such system is, that a containment of a reactor effected by serious accident has to be cooled by water brought from outside, which flows into a shaft of the reactor from a pool performed on a floor of the containment. Heated water evaporates and escapes in form of vapor to the containment, by which it is pressured and the construction of it is heated. If such situation is not solved, risk of rupture of integrity of the containment by the higher pressure, which is above secure limit of the construction, may occur. It is necessary to avert pressurization of such space under the defined secure limit and stabilize pressure in the containment at low limit.
[004] Several of technical solutions and suggestions how to take heat from such area exists. However, performance and construction of the containments differs one of the other. Very often a source of an energy is a steam turbine, or a circulation of cooling medium in a primary circuit is not separated.
[005] A long-term heat removal system is presented in a document EP 3451 346 A1. The system comprises a cold circuit and a hot circuit, where a cold circuit comprises a pump station connected by its one end to a source of cooling medium of the cold circuit and by its second end to a turbine, from which the cooling liquid is led through a cold circuit of a cooler back to the source of the cooling medium of the cold circuit. The hot circuit comprises a pump of a heat circuit connected by its input to a source of a cooling medium of the heat circuit, specifically a floor of the containment, and by its output to the hot circuit of the cooler, from which the cooling medium is led to a shower. A disadvantage of such solution is, that in case, when the temperature of the cooling medium on the bottom of the containment reaches its boiling point, pumping of it is very difficult, because not only liquid is transported but also gas, which influences quality of interchange in the heat exchanger.
[006] The aim of the invention is to present a long-term heat removal system from a containment, which is able to eliminate the above mentioned disadvantages.
Feature of the Invention
[007] The above mentioned disadvantages are considerably eliminated by use of a long-term heat removal system from containment comprises a cold circuit and a hot circuit, where the cold circuit comprises a feed pump station on its one side connected to a source of cooling medium of the cold circuit and by its second side to a small impurity filter, which is connected to a main pump station, which is connected by inlet closing valve to a turbine, and then by cold circuit of a cooler and an outlet closing valve to the source of cooling medium of the cold circuit, the hot circuit comprises a pump of the hot circuit connected on its outlet by a hot circuit of the cooler to a shower arranged in the containment, and on inlet by a mechanical strainer to a source of cooling medium of the hot circuit, where the main pump station is connected by a primary extra cooling branch of the heat circuit to the inlet of the pump of the hot circuit, by which the cooling medium of the cold circuit is mixed with the cooling medium of the hot circuit.
[008] In an advantageous embodiment the cold circuit comprises a primary extra cooling branch of the cold circuit, which connects the inlet of the small impurity filter with the source of cooling medium of the cold circuit and/or the secondary extra cooling branch of the cold circuit, which connects the outlet of the main pump station with the source of cooling medium of the cold circuit.
[009] In another advantageous embodiment the hot circuit comprises a secondary extra cooling branch of the hot circuit, which connects the outlet of the hot circuit of the cooler with the inlet of the pump. Description of the drawing
[0010] The invention will be further explained by using the drawing Fig. 1, which presents the long-term heat removal system from a containment according to the invention.
Preferred Embodiments of the Invention
[0011] The long-term heat removal system from a containment according to the invention, presented in Fig. 1, comprises a cold circuit and a hot circuit.
[0012] The cold circuit comprises a feed pump station 1 on its one side connected to a source of cooling medium of the cold circuit and by its second side to a small impurity filter 2, which is connected to a main pump station 3, which is connected by inlet closing valve 4 to a turbine 5, and then by cold circuit of a cooler 6 and an outlet closing valve 7 to the source of cooling medium of the cold circuit, by which the cold circuit is closed.
[0013] The hot circuit comprises a pump 8 of the hot circuit connected on its outlet by a hot circuit of the cooler 6 to a shower 9 arranged in the containment 10, and on inlet by a mechanical strainer 11 to a source of cooling medium of the hot circuit.
[0014] Furthermore, the main pump station 3 is connected by a primary extra cooling branch 19a of the heat circuit, which comprises a closing valve 20a, to the inlet of the pump 8 of the hot circuit, by which additional cooling of the cooling medium of the hot circuit floating to the pump 8 is performed, to ensure its correct function.
[0015] As an example, the source of the cooling medium of the cold circuit is a pool 12 of a cooling tower 13. The cooling medium is for example water.
[0016] In advance, the cold circuit is provided by desedimentation branch 14, which connects the small impurity filter 2 with a desedimentation tank 15. If it is noticed by sensors arranged in the filter 2, that the filter is clogged, its washout is performed and sediments are flushed into the desedimentation tank 15. The desedimentation branch 14 is provided by desedimentation valve 16.
[0017] Advantageously, the cold circuit is provided by one or two extra cooling branches 17a and 17b of the cold circuit. The primary extra cooling branch 17a of the cold circuit connects the inlet of the small impurity filter 2 with the source of cooling medium of the cold circuit. The secondary extra cooling branch 17b of the cold circuit connects the outlet of the main pump station 3 with the source of cooling medium of the cold circuit. Both of those branches 17a, 17b of the cold circuit are possibly activated by regulation valves 18a, 18b, when temperature of the cooling medium of the cold circuit takes over predetermined limit.
[0018] The source of the cooling medium of the hot circuit is the bottom part of the containment 10, which is filled by the shower 9. The cooling medium comprises a mixture of water and boron acid.
[0019] In the presented embodiment the turbine 5 and the pump 8 form one compact aggregate with single rotor system, i.e. a turbopump.
[0020] The hot circuit is advantageously provided with a secondary extra cooling branch 19b of the hot circuit, which comprises a closing valve 20b, which connects the outlet of the hot circuit of the cooler 6 with the inlet of the pump 8. Because of that, limited capacity of the cooling medium in the containment 10 is solved, which should be insufficient for long-term heat transfer. If the extra cooling branch is missing, a critical temperature should be reached in few hours.
[0021] Interconnection of the above mentioned components is performed by hoses or pipes.
[0022] The functional principle of the long-term heat removal system from a containment according to the invention presented by the above mentioned embodiment of an example follows:
[0023] The feed pump station 1 takes cold water from the pool 12 under the cooling tower 13 of a power plant, respectively from the reservoirs of fan cooling towers 13, and transports it through the impurity filter 2, which is intended for ensuring quality of the water, to the main pump station 3, Both pump stations 1 and 3 comprise pump aggregates with a thermic diesel actuator. Pressurized water is than led from the main pump station 3 to the inlet of the containment 10 of the reactor block. After that, it is led to a turbine 5 of the hydrodynamic pump aggregate and waste water from the turbine 5 of the hydrodynamic aggregate is than led to the cold circuit of a heat exchanger, respectively called the cooler 6, where it takes hot energy from pumped cooling medium of the hot circuit, and after it is heated it leaves the containment 10 of the reactor block and is taken back to the pool 12 under the cooling tower 13 or into the reservoirs of the fan cooling towers 13. The pump 8 of the hot circuit sucks the hot mixture of water and boron acid from the bottom of the containment 10, filtrates it through the mechanical screen 11 and leads it to the hot circuit of the hot exchanger, respectively the cooler 6, and then to the dropping system, specifically the shower 9, arranged inside the containment 10, where it ensures required cooling effect of imoortant comoonents of the containment 10 of the reactor. [0024] The long-term heat removal system according to the invention is fully autonomous, independent to technology of used devices of the nuclear reactor, and to an external power source, specifically a source of electricity. Possible exceptions should be components of the system, which are placed out of the containment and freely accessible even in time of serious accident, even though for a limited time, for example for the time required for refilling of fuel Into a thermic engine, etc.
[0025] Particularly, the long-term heat removal system from a containment according to the invention is intended for nuclear power plants with a light water reactor of a WER type,

Claims

Claims
1. Long-term heat removal system from containment comprises a cold circuit and a hot circuit, where
- the cold circuit comprises a feed pump station 1 on its one side connected to a source of cooling medium of the cold circuit and by its second side to a small impurity filter 2, which is connected to a main pump station 3, which is connected by inlet closing valve 4 to a turbine 5, and then by cold circuit of a cooler 6 and an outlet closing valve 7 to the source of cooling medium of the cold circuit,
- the hot circuit comprises a pump 8 of the hot circuit connected on its outlet by a hot circuit of the cooler 6 to a shower 9 arranged in the containment 10, and on inlet by a mechanical strainer 11 to a source of cooling medium of the hot circuit, characterized in, that
- the main pump station 3 is connected by a primary extra cooling branch 19a of the heat circuit to the inlet of the pump 8 of the hot circuit, by which the cooling medium of the cold circuit is mixed with the cooling medium of the hot circuit.
2. Long-term heat removal system according to the claim 1, characterized in, that the cold circuit comprises a primary extra cooling branch 17a of the cold circuit, which connects the inlet of the small impurity filter 2 with the source of cooling medium of the cold circuit and/or the secondary extra cooling branch 17b of the cold circuit, which connects the outlet of the main pump station 3 with the source of cooling medium of the cold circuit.
3. Long-term heat removal system according to the claim 1 or 2, characterized in, that the hot circuit comprises a secondary extra cooling branch 19b of the hot circuit, which connects the outlet of the hot circuit of the cooler 6 with the inlet of the pump 8.
PCT/CZ2020/050062 2019-09-11 2020-09-02 Long-term heat removal system from a containment WO2021047697A1 (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
HU2200126A HUP2200126A1 (en) 2019-09-11 2020-09-02 Long-term heat removal system from a containment
FI20225195A FI130325B (en) 2019-09-11 2020-09-02 Long-term heat removal system from a containment

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CZPV2019-576 2019-09-11
CZ2019576A CZ2019576A3 (en) 2019-09-11 2019-09-11 Long-term heat removal system from the hermetic zone

Publications (1)

Publication Number Publication Date
WO2021047697A1 true WO2021047697A1 (en) 2021-03-18

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PCT/CZ2020/050062 WO2021047697A1 (en) 2019-09-11 2020-09-02 Long-term heat removal system from a containment

Country Status (5)

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CZ (1) CZ2019576A3 (en)
FI (1) FI130325B (en)
HU (1) HUP2200126A1 (en)
SK (1) SK289115B6 (en)
WO (1) WO2021047697A1 (en)

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2013096928A (en) * 2011-11-04 2013-05-20 Toshiba Corp Reactor facilities and reactor containment vessel cooling system
GB2531479A (en) * 2013-07-26 2016-04-20 China Nuclear Power Eng Co Ltd Mid-long term cooling method and system for containment and spent fuel pool in nuclear power plant after occurring accident
EP3451346A1 (en) 2017-09-01 2019-03-06 Westinghouse Electric Germany GmbH Containment cooling system

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2942937C2 (en) * 1979-10-24 1984-10-18 Brown Boveri Reaktor GmbH, 6800 Mannheim Device for residual heat removal and / or for emergency cooling of a water-cooled nuclear reactor plant
JP2013148438A (en) * 2012-01-19 2013-08-01 Toshiba Corp Emergency cooling system, and nuclear reactor facility
US10685751B2 (en) * 2017-11-08 2020-06-16 Palvannanathan Ganesan Floating nuclear power reactor with a self-cooling containment structure and an emergency heat exchange system

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2013096928A (en) * 2011-11-04 2013-05-20 Toshiba Corp Reactor facilities and reactor containment vessel cooling system
GB2531479A (en) * 2013-07-26 2016-04-20 China Nuclear Power Eng Co Ltd Mid-long term cooling method and system for containment and spent fuel pool in nuclear power plant after occurring accident
EP3451346A1 (en) 2017-09-01 2019-03-06 Westinghouse Electric Germany GmbH Containment cooling system

Also Published As

Publication number Publication date
FI130325B (en) 2023-06-20
CZ308670B6 (en) 2021-02-03
SK500142022A3 (en) 2022-05-25
HUP2200126A1 (en) 2022-07-28
SK289115B6 (en) 2023-09-27
CZ2019576A3 (en) 2021-02-03

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