US20110314858A1 - Reactor containment vessel cooling system, reactor containment vessel, and reactor containment vessel cooling method - Google Patents

Reactor containment vessel cooling system, reactor containment vessel, and reactor containment vessel cooling method Download PDF

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Publication number
US20110314858A1
US20110314858A1 US13/204,000 US201013204000A US2011314858A1 US 20110314858 A1 US20110314858 A1 US 20110314858A1 US 201013204000 A US201013204000 A US 201013204000A US 2011314858 A1 US2011314858 A1 US 2011314858A1
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United States
Prior art keywords
condensate
containment vessel
reactor containment
reactor
water vapor
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Abandoned
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US13/204,000
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English (en)
Inventor
Mika Tahara
Mikihide Nakamaru
Akira Murase
Ryoichi HAMAZAKI
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Toshiba Corp
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Toshiba Corp
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Assigned to KABUSHIKI KAISHA TOSHIBA reassignment KABUSHIKI KAISHA TOSHIBA ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: HAMAZAKI, RYOICHI, MURASE, AKIRA, NAKAMARU, MIKIHIDE, TAHARA, MIKA
Publication of US20110314858A1 publication Critical patent/US20110314858A1/en
Abandoned legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004—Pressure suppression
    • 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
    • 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 relates to a reactor containment vessel cooling technology for maintaining safety of the environment around a reactor by removing decay heat generated when reactor water is accidentally lost, and particularly, to a reactor containment vessel cooling technology for producing emergency cooling water by using water vapor pressure in a reactor containment vessel as a drive force, and the present invention includes a reactor containment vessel cooling system, a reactor containment vessel, and a reactor containment vessel cooling method.
  • a nuclear reactor includes an emergency core cooling system and a decay heat removing system for maintaining safety of the environment around the reactor by cooling the inside of a reactor containment vessel with water to remove decay heat in case reactor water is accidentally lost.
  • a full accident countermeasure guideline has been provided by introducing cooling water from an external water source to the reactor containment vessel to reliably cool the reactor containment vessel.
  • the reactor containment vessel cooling technology described above requires no pump or other electric drive sources to cool the inside of the reactor containment vessel, the reactor containment vessel can be cooled even in a case where the power supply responsible for the entire nuclear facility is accidentally lost.
  • the present invention has been made in view of the circumstances of the prior art described above, and an object of the present invention is to provide a reactor containment vessel cooling system, a reactor containment vessel, and a reactor containment vessel cooling method that prevent cooling capability and structural integrity of the reactor containment vessel cooling system from being decreased by lowering or raising the temperature of water vapor and gases acquired by the reactor containment vessel cooling system.
  • the present invention provides a reactor containment vessel cooling system that cools the reactor containment vessel by acquiring water vapor in a reactor containment vessel and using water vapor pressure in the vessel as a drive force to thereby condense the acquired water vapor into condensate and cool the reactor containment vessel with the condensate
  • the reactor containment vessel cooling system comprising a heat exchange pool that is arranged apart from a dry well and a suppression chamber in the reactor containment vessel and stores a medium for cooling acquired water vapor, a heat exchanger that is immersed in the heat exchange pool, acquires water vapor from the dry well in the reactor containment vessel, and perform heat exchange between the water vapor and the cooling medium in the heat exchange pool so as to generate condensate, and a condensate drain pipe that extracts the condensate from the heat exchanger and guides and discharges the condensate toward a reactor pressure vessel.
  • the reactor containment vessel cooling system having the features described above may employ the following preferred aspects.
  • the condensate drain pipe may discharge the condensate in such a way that the condensate flows down along a side surface of a thermally insulating member that surrounds the reactor pressure vessel.
  • the condensate drain pipe may discharge the condensate from a position above a reactor shielding wall provided outside the thermally insulating member at a side surface of the thermally insulating member.
  • the condensate drain pipe may include a ring-shaped header tube which circumferentially surrounds the thermally insulating member and through which the condensate flows and a plurality of condensate discharge ports provided at intervals along the header tube in a circumferential direction thereof.
  • the condensate drain pipe may discharge the condensate in such a way that the condensate flows down along a side surface of the reactor pressure vessel.
  • the condensate drain pipe may discharge the condensate from a position above a reactor shielding wall at a side surface of the reactor pressure vessel.
  • the condensate drain pipe may include a ring-shaped header tube which circumferentially surrounds the reactor pressure vessel and through which the condensate flows and a plurality of discharge ports which are provided at intervals along the header tube in a circumferential direction thereof and through which the condensate is discharged.
  • Each of the discharge ports may be formed of a nozzle penetrating a thermally insulating member that surrounds the reactor pressure vessel from outside to inside.
  • the header tube may be embedded in the thermally insulating member.
  • a part of the condensate drain pipe may be replaced with a curved tube having a downwardly convex shape.
  • the present invention provides a reactor containment vessel including: a reactor pressure vessel that accommodates a core; a reactor shielding wall provided to surround an outer circumferential surface of the reactor pressure vessel; a dry well that forms a space that accommodates the reactor pressure vessel; a suppression chamber for controlling internal pressure in the reactor containment vessel: and a reactor containment vessel cooling system that acquires water vapor in the reactor containment vessel by using water vapor pressure in the vessel as a drive force, condenses the acquired water vapor into condensate, and cools the reactor containment vessel with the condensate.
  • the reactor containment, vessel cooling system has the structural features described above.
  • the present invention provides a reactor containment vessel cooling method for cooling the reactor containment vessel by acquiring water vapor in a reactor containment vessel, using water vapor pressure in the vessel, condensing the acquired water vapor into condensate, and cooling an internal space of the reactor containment vessel with the condensate, the reactor containment vessel cooling method including: storing a water vapor cooling medium in a position arranged apart from a dry well and a suppression chamber in the reactor containment vessel, and acquiring water vapor from the dry well in the reactor containment vessel, performing heat exchange between the water vapor and the cooling medium so as to convert the water vapor into condensate, and guiding and discharging the condensate toward a reactor pressure vessel.
  • the present invention can prevent the cooling capability and structural integrity of a reactor containment vessel cooling system from decreasing by lowering the temperature of water vapor and gases acquired by the reactor containment vessel cooling system.
  • FIG. 1 is a front sectional view showing a first embodiment of a reactor containment vessel cooling system according to the present invention.
  • FIG. 2 is an enlarged sectional view of an essential portion of the react or containment vessel cooling system shown in FIG. 1 , including FIG. 2A showing a layout of a condensate drain pipe and FIG. 2B being an enlarged view of an encircled portion P shown in FIG. 2A .
  • FIG. 3 is a perspective view of the condensate drain pipe shown in FIG. 2A .
  • FIG. 4 is a graph explaining function of the reactor containment vessel cooling system shown in FIG. 1 .
  • FIG. 5 is a sectional view showing a second embodiment of the reactor containment vessel cooling system according to the present invention.
  • FIG. 6 is an enlarged sectional view of an essential portion showing a third embodiment of the reactor containment vessel cooling system according to the present invention.
  • FIG. 1 is a front sectional view showing a first embodiment of a reactor containment vessel cooling system according to the present invention.
  • a reactor containment vessel cooling system 20 according to the first embodiment is provided inside or outside a reactor containment vessel 10 .
  • the reactor containment vessel 10 is provided so as to surround reactor pressure vessel 12 that accommodates a core 11 , a react or shielding wall 13 and other reactor structures or components.
  • the reactor containment vessel 10 has a structure capable of preventing fission products from being released into the atmosphere even in a case where a primary steam tube 14 or any of her component is broken and hence reactor water in the reactor pressure vessel 12 is lost and a fuel is melt or damaged.
  • the reactor containment vessel 10 includes a dry well 15 (upper dry well 15 a and lower dry well 15 b ) that forms a space for accommodating the reactor pressure vessel 12 and a suppression chamber (wet well) 16 that is responsible for controlling the internal pressure in the reactor containment vessel 10 .
  • the dry well 15 and the suppression chamber 16 communicate with each other via vent tube 18 .
  • the suppression chamber 16 includes a suppression pool 17 that stores emergency cooling water and surrounds the reactor pressure vessel 12 .
  • the reactor containment vessel 10 is provided with an emergency core cooling system and a decay heat removing system (both systems are omitted in FIG. 1 ), which are activated to remove decay heat generated around the core 11 when the primary steam tube 14 is accidentally broken and hence reactor water is lost.
  • the emergency core cooling system and a decay heat removing system are activated, the dry well 15 is filled with water vapor originating from the reactor water having leaked out of the reactor pressure vessel 12 through the broken portion of the tube and water vapor originating from the water acquired from the suppression pool 17 by the emergency core cooling system.
  • the water vapor with which the dry well 15 is filled passes through the vent tube 18 and travels into the suppression pool 17 , where the water vapor is absorbed and condensed. The increase in internal pressure in the reactor containment vessel 10 is thus reduced.
  • the reactor containment vessel cooling system 20 condenses the water vapor, with which the reactor pressure vessel 12 is filled, into condensate and cools the reactor containment vessel 10 with the condensate in order to reinforce the cooling capability of the emergency core cooling system and a decay heat removing system.
  • the reactor containment vessel cooling system 20 includes, as shown in FIG. 1 , a heat exchange pool 21 , a heat exchanger 22 , a water vapor sucking tube 23 , a noncondensable gas vent pipe 24 , and a condensate drain pipe 25 .
  • the heat exchange pool 21 which is so provided that it is thermally and spatially set apart from the dry well 15 and the suppression chamber 16 in the reactor containment vessel 10 , stores a medium for cooling water vapor with which an upper portion of the upper dry well 15 a in the reactor containment vessel 10 is filled.
  • the cooling medium is, for example, light water.
  • the heat exchanger 22 which includes a heat transfer tube 22 a made of a material having excellent heat conductivity, is immersed in the heat exchange pool 21 .
  • the heat exchanger 22 allows water vapor introduced into the heat transfer tube 22 a to exchange heat with the cooling medium in the heat exchange pool 21 so that the water vapor becomes condensate.
  • the water vapor sucking tube 23 has a sucking port positioned in the upper dry well 15 a , sucks the water vapor with which the upper dry well 15 a is filled, and delivers the water vapor into the heat transfer tube 22 a .
  • the operation of sucking the water vapor into the water vapor sucking tube 23 is driven by the water vapor pressure in the reactor containment vessel 10 .
  • the noncondensable gas vent pipe 24 extracts a noncondensable gas delivered along with the water vapor into the heat transfer tube 22 a out of the heat transfer tube 22 a to maintain the heat exchanging capability between the water vapor in the heat transfer tube 22 a and the cooling medium in the heat exchange pool 21 .
  • the noncondensable gas vent pipe 24 extends from the exit port of the heat transfer tube 22 a , which forms the heat exchanger 22 , toward the suppression chamber 16 , and the distal end of the noncondensable gas vent pipe 24 is immersed in the suppression pool 17 .
  • the condensate drain pipe 25 extracts the condensate from the heat exchanger 22 and guides and discharges the condensate toward the reactor pressure vessel 12 .
  • the operation of extracting and guiding the condensate is driven by the water vapor pressure in the reactor containment vessel 10 and the gravity.
  • FIG. 2 is an enlarged sectional view of an essential portion of the reactor containment vessel cooling system 20 shown in FIG. 1 .
  • FIG. 2A is a cross-sectional view showing the layout of the condensate drain pipe 25 .
  • FIG. 2B is an enlarged sectional view of the portion “P” shown in FIG. 2A .
  • FIG. 3 is a perspective view of the condensate drain pipe 25 shown in FIG. 2A .
  • the distal end of the condensate drain pipe 25 is formed of a ring-shaped header tube 26 which circumferentially surrounds a thermally insulating member 19 that circumferentially covers the reactor pressure vessel 12 and through which the condensate extracted from the heat exchanger 22 flows around the thermally insulating member 19 .
  • the thermally insulating member 19 which is made of a metallic material, suppresses heat dissipation from the reactor pressure vessel 12 during normal operation of the reactor.
  • the header tube 26 has a plurality of discharge ports 27 provided at intervals along the circumferential direction of the header tube 26 .
  • the angle and layout of the discharge ports 27 are set so as to face the gap formed between the reactor shielding wall 13 and the thermally insulating member 19 and to discharge the condensate flowing through the header tube 26 at the side surface of the thermally insulating member 19 , as shown in FIG. 2B .
  • the symbol D in FIG. 2B represents the direction in which the condensate is discharged from the header tube 26 .
  • the reactor containment vessel cooling system 20 of the structure mentioned above will attain the following functions and effects.
  • the thus configured reactor containment vessel cooling system 20 according to the present embodiment provides the following advantageous effects:
  • the reactor containment vessel cooling system 20 includes: the heat exchange pool 21 , which is installed apart from the dry well 15 and the suppression chamber 16 in the reactor containment vessel 10 and stores a medium for cooling water vapor; the heat exchanger 22 , which is immersed in the heat exchange pool 21 , extracts water vapor from the dry well 15 in the reactor containment vessel 10 , and allows the water vapor to exchange heat with the cooling medium in the heat exchange pool 21 so as to convert the water vapor into condensate; and the condensate drain pipe 25 , which extracts the condensate from the heat exchanger 22 and guides and discharges the condensate at the reactor pressure vessel 12 .
  • the water vapor produced in the dry well 15 as described above undergoes a heat exchange process and becomes condensate, and the condensate is discharged around the reactor pressure vessel 12 .
  • the discharged condensate efficiently removes decay heat generated by radioactive nuclides attached to the reactor pressure vessel 12 , thus suppressing increase in the temperature of the atmosphere in the dry well 15 due to the decay heat.
  • the temperature of the water vapor and gases introduced into the reactor containment vessel cooling system 20 can be lowered, and degradation in cooling capability and structural integrity of the reactor containment, vessel cooling system 20 can be suppressed.
  • the condensate drain pipe 25 discharges condensate from a position above the reactor shielding wall 13 at the side surface of the thermally insulating member 19 , the condensate flows down along the side surface of the thermally insulating member 19 .
  • the condensate can indirectly absorb the heat accumulated in the thermally insulating member 19 , that is, decay heat generated by radioactive nuclides attached to the reactor pressure vessel 12 over a wide area of the thermally insulating member 19 .
  • the condensate that has not evaporated but has been left in the process, in which the condensate flows down the thermally insulating member, 19 is accumulated between the reactor shielding wall 13 and the thermally insulating member 19 and overflows through an opening 13 a for inter-pipe communication, such as a recirculation nozzle provided through the reactor shielding wall 13 .
  • the overflow condensate absorbs the decay heat and becomes water vapor, which passes through the vent tube 18 , eventually flows into the suppression pool 17 , at which a part of the water vapor is cooled and condensed, and the rest of the water vapor travels to the upper dry well 15 a and enters the heat exchanger 22 .
  • FIG. 4 shows a graph illustrating the relationship between the proportion of the partial pressure of a noncondensable gas (ratio of noncondensable gas partial pressure to atmospheric pressure) and a degradation factor (index representing relative performance) of a heat exchange-type reactor containment vessel cooling system shown in Non-Patent Document 1.
  • the reactor containment vessel cooling system 20 since the decay heat generated by radioactive nuclides attached to the reactor pressure vessel 12 efficiently evaporates condensate, the proportion of water vapor in the upper dry well 15 a is greater than that in the lower dry well 15 b . Therefore, the proportion of the partial pressure of a noncondensable gas in the upper dry well 15 a is lower than that in the lower dry well 15 b .
  • the reactor containment vessel cooling system 20 primarily extracts water vapor from the upper dry well 15 a , where the proportion of the partial pressure of the noncondensable gas is relatively small, thus suppressing the decreasing in heat exchange capability of the heat exchanger 22 , that is, decreasing in cooling capability of the reactor containment vessel cooling system 20 .
  • the condensate drain pipe 25 includes the ring-shaped header tube 26 , which circumferentially surrounds the thermally insulating member 19 and through which condensate flows, and the plurality of condensate discharge ports 27 provided at intervals along the header tube 26 in the circumferential direction thereof.
  • FIG. 5 is an enlarged sectional view of a key portion showing a second embodiment of the reactor containment vessel cooling system according to the present invention.
  • the present embodiment is an example in which the condensate drain pipe 25 in the reactor containment vessel cooling system 20 in the first embodiment is configured differently.
  • components or members similar to those in the first embodiment are added with the same reference numerals, and components different from those in the first embodiment or added thereto are labeled with “A” in the following description.
  • a condensate drain pipe 25 A in the present embodiment includes a header tube 26 A.
  • the header tube 26 A is formed of a ring-shaped pipe through which condensate extracted from the heat exchanger 22 (see FIG. 1 ) flows, as in the first embodiment, but is embedded in the thermally insulating member 19 and circumferentially surrounds the reactor pressure vessel 12 .
  • the header tube 26 A has a plurality of discharge ports 27 A provided at intervals along the circumferential direction of the header tube 26 A.
  • the angle and layout of the discharge ports 27 A are arranged so as to face the gap formed between the reactor pressure vessel 12 and the thermally insulating member 19 and to discharge the condensate flowing through the header tube 26 A at the side surface of the reactor pressure vessel 12 .
  • the condensate drain pipe 25 A further includes a folded portion (bent portion) 28 A, as shown in FIG. 5 .
  • the folded portion 28 A is a downwardly convex curved tube that replaces a portion of the condensate drain pipe 25 A and holds water therein during the normal operation of the reactor.
  • the curved tube is formed of a U-shaped or V-shaped tube.
  • the symbol W in FIG. 5 represents a water surface.
  • the reactor containment vessel cooling system 20 A can provide not only the advantageous effect (1) provided in the first embodiment but also the following advantageous effects (4) to (6).
  • the condensate drain pipe 25 A discharges condensate at the side surface of the reactor pressure vessel 12 instead of the thermally insulating member 19 , the condensate flows down along the side surface of the reactor pressure vessel 12 .
  • the condensate directly absorbs the decay heat generated by the radioactive nuclides attached to the reactor pressure vessel 12 , whereby the advantageous effect (1) provided in the first embodiment is enhanced.
  • the condensate flowing down along the reactor pressure vessel 12 travels, for example, through the gap between guide tubes (not shown) of a control rod drive mechanism into the lower dry well 15 b (see FIG. 1 ), where the condensate becomes water vapor.
  • the water vapor originating from the condensate passes through the vent tube 18 and eventually flows into the suppression pool 17 , where a part of the water vapor is cooled and condensed, and the rest of the water vapor travels to the upper dry well 15 a and enters into the heat exchanger 22 .
  • a part of the condensate drain pipe 25 A is replaced with the U-shaped tube having a convexly downward shape, and water is held in the U-shaped tube.
  • the water held in the U-shaped tube works as a barrier, which substantially prevents the atmosphere gas with which the structural space between the reactor pressure vessel 12 and the thermally insulating member 19 from traveling toward the upstream side of the condensate drain pipe 25 A. That is, the heat accumulated between the reactor pressure vessel 12 and the thermally insulating member 19 unlikely leaks through the condensate drain pipe 25 A.
  • condensate can be directly discharged at the reactor pressure vessel 12 without degradation of the capability of thermally insulating the reactor pressure vessel 12 during the normal operation of the reactor.
  • FIG. 6 is an enlarged sectional view of an essential portion representing a third embodiment of the reactor containment vessel cooling system 20 B according to the present invention.
  • the present embodiment is an example in which the condensate discharge parts 27 A in the reactor containment vessel cooling system 20 A in the second embodiment are configured differently.
  • components or members similar to those in the second embodiment are added with the same reference numerals, and components different from those in the second embodiment or added thereto are labeled with “B” in the following description.
  • the reactor containment vessel cooling system 20 B includes nozzles 29 B, as shown in FIG. 6 .
  • Each of the nozzles 29 B extends from the edge of the corresponding discharge port 27 A (see FIG. 5 ) in the second embodiment and forms a discharge portion through which the condensate extracted from the heat exchanger 22 (see FIG. 1 ) is discharged.
  • the nozzles 29 are so provided that they penetrate through the thermally insulating member 19 from outside to inside, and the angle of the nozzles 29 are arranged so as to discharge the condensate at the side surface of a reactor pressure vessel 12 .
  • the tube wall of each of the nozzles 29 B is in close contact with the thermally insulating member 19 .
  • the reactor containment vessel cooling system 20 B can provide not only the advantageous effect (1) provided in the first embodiment and the advantageous effects (4) to (6) provided in the second embodiment but also the following advantageous effect (7).
  • the discharge ports of the condensate drain pipe 25 B are formed of the nozzles 29 B, which penetrate through the thermally insulating member that surrounds the reactor pressure vessel 12 from outside to inside. That is, in the configuration in which the condensate is directly discharged at the reactor pressure vessel 12 , the atmosphere gas with which the structural space between the reactor pressure vessel 12 and the thermally insulating member 19 is filled unlikely leaks out of the thermally insulating member 19 . As a result, the condensate can be directly discharged at the reactor pressure vessel 12 without degradation of the capability of thermally insulating the reactor pressure vessel 12 during the normal operation of the reactor.
  • the condensate drain pipe is used to discharge condensate at the side surface of the thermally insulating member
  • the condensate may alternatively be discharged at the top surface of the thermally insulating member.
  • the second and third embodiments have been described with reference to the case where the condensate drain pipe is used to discharge condensate at the side surface of the reactor pressure vessel
  • the condensate may alternatively be discharged at the top of the reactor pressure vessel. In this configuration, the condensate flows over a wider area of the reactor pressure vessel, whereby decay heat held by the reactor pressure vessel can be more effectively removed.
  • the second embodiment has been described with reference to the case where water is held in the curved tube (such as U-shaped tube) during normal operation of the reactor, water is not necessarily held in the U-shaped tube because the thermal stratification that occurs in the U-shaped tube prevents the atmosphere gas between the reactor pressure vessel and the thermally insulating member from traveling to the upstream side of the U-shaped tube.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
US13/204,000 2009-03-02 2010-03-01 Reactor containment vessel cooling system, reactor containment vessel, and reactor containment vessel cooling method Abandoned US20110314858A1 (en)

Applications Claiming Priority (3)

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JP2009-048348 2009-03-02
JP2009048348A JP2010203858A (ja) 2009-03-02 2009-03-02 原子炉格納容器冷却設備、原子炉格納容器および原子炉格納容器冷却方法
PCT/JP2010/053243 WO2010101112A1 (ja) 2009-03-02 2010-03-01 原子炉格納容器冷却設備、原子炉格納容器および原子炉格納容器冷却方法

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US20150170772A1 (en) * 2012-05-21 2015-06-18 Smr Inventec, Llc Component cooling water system for nuclear power plant
US20170004892A1 (en) * 2013-12-03 2017-01-05 Korea Atomic Energy Research Institute Passive cooling system of containment building and nuclear power plant comprising same
CN107093470A (zh) * 2017-03-10 2017-08-25 中国核电工程有限公司 一种加强冷却的安全壳抑压系统
US9786393B2 (en) 2012-05-21 2017-10-10 Smr Inventec, Llc Passive reactor containment protection system
US10665354B2 (en) 2012-05-21 2020-05-26 Smr Inventec, Llc Loss-of-coolant accident reactor cooling system
US10720249B2 (en) 2012-05-21 2020-07-21 Smr Inventec, Llc Passive reactor cooling system
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US11901088B2 (en) 2012-05-04 2024-02-13 Smr Inventec, Llc Method of heating primary coolant outside of primary coolant loop during a reactor startup operation
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JP6071404B2 (ja) * 2012-10-12 2017-02-01 株式会社東芝 原子力プラントおよび静的格納容器冷却系
US9738440B2 (en) 2012-12-20 2017-08-22 Ge-Hitachi Nuclear Energy Americas Llc Entrainment-reducing assembly, system including the assembly, and method of reducing entrainment of gases with the assembly
JP6004438B2 (ja) * 2013-03-18 2016-10-05 日立Ｇｅニュークリア・エナジー株式会社 原子炉冷却システム
KR101973996B1 (ko) * 2017-05-15 2019-04-30 한국원자력연구원 원자로용기 외벽 냉각 및 발전 시스템
JP7045966B2 (ja) * 2018-09-20 2022-04-01 日立Ｇｅニュークリア・エナジー株式会社 原子力プラント及びその運転方法
CN111785399B (zh) * 2020-07-06 2023-06-20 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) 一种用于海洋核动力平台热量导出的系统

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