GB1421826A - Convective emergency cooling systems of nuclear rectors - Google Patents

Convective emergency cooling systems of nuclear rectors

Info

Publication number
GB1421826A
GB1421826A GB1674673A GB1674673A GB1421826A GB 1421826 A GB1421826 A GB 1421826A GB 1674673 A GB1674673 A GB 1674673A GB 1674673 A GB1674673 A GB 1674673A GB 1421826 A GB1421826 A GB 1421826A
Authority
GB
United Kingdom
Prior art keywords
flow
breeder
cooling
zone
reactor
Prior art date
Legal status (The legal status 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 status listed.)
Expired
Application number
GB1674673A
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Interatom Internationale Atomreaktorbau GmbH
Original Assignee
Interatom Internationale Atomreaktorbau GmbH
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 Interatom Internationale Atomreaktorbau GmbH filed Critical Interatom Internationale Atomreaktorbau GmbH
Publication of GB1421826A publication Critical patent/GB1421826A/en
Expired legal-status Critical Current

Links

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
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

1421826 Nuclear reactor emergency cooling INTERATOM INTERNATIONALE ATOMREAKTORBAU GmbH 6 April 1973 [8 April 1972] 16746/73 Heading G6C Upon failure of the primary cooling of a reactor, e.g. a sodium-cooled, fast breeder, emergency cooling is set up by natural circulation in a flow direction opposite to that in part of the reactor during normal, primary cooling. The reactor core includes a fission zone 2 and radial and axial breeding zones 3, 4. Surrounding the core is an annular space 8 for storage of " hot " fission and breeder elements, and an outer, annular space 9 in which are disposed emergency cooling heat-exchangers 10 each in a protective shield 11 with an open bottom and inlet apertures 13 below the minimum coolant level 12. Upon failure of the primary cooling system, natural-flow circulation commences automatically with flow directions in the various regions as indicated by the arrows, the flow-direction in the breeder zone 3 being reversed relative to normal cooling flow. Flow diodes 16 are arranged to facilitate the natural-circulation flow and restrict the amount of coolant which bypasses the fission zone during normal, primary cooling. The diodes may be of a variety of forms such as direction-dependent throttles or diaphragms, or valves actuated automatically in response to coolant pressure or temperature. In a particularly suitable form, radial guide vanes are offset from one another in a helical arrangement. The coolant passes through gas bubble separators 15 prior to entering the lower breeder zone 4.
GB1674673A 1972-04-08 1973-04-06 Convective emergency cooling systems of nuclear rectors Expired GB1421826A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2217057A DE2217057C2 (en) 1972-04-08 1972-04-08 Natural circulation - emergency cooling for nuclear reactors

Publications (1)

Publication Number Publication Date
GB1421826A true GB1421826A (en) 1976-01-21

Family

ID=5841432

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1674673A Expired GB1421826A (en) 1972-04-08 1973-04-06 Convective emergency cooling systems of nuclear rectors

Country Status (5)

Country Link
JP (1) JPS5916238B2 (en)
DE (1) DE2217057C2 (en)
FR (1) FR2179839B3 (en)
GB (1) GB1421826A (en)
IT (1) IT982688B (en)

Cited By (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4115192A (en) * 1976-07-06 1978-09-19 Commissariat A L'energie Atomique Fast neutron nuclear reactor
US4186051A (en) * 1976-05-13 1980-01-29 Interatom, Internationale Atomreaktorbau Gmbh Nuclear energy plant with improved device for removing after-heat and emergency heat
US4342721A (en) * 1978-03-07 1982-08-03 Commissariat A L'energie Atomique Fast nuclear reactor
US4526742A (en) * 1981-03-30 1985-07-02 Ab Asea-Atom Nuclear reactor plant
GB2163890A (en) * 1984-08-29 1986-03-05 Ga Technologies Inc Nuclear reactor
US4608224A (en) * 1980-07-04 1986-08-26 Service National Electricite De France Nuclear reactor cooled by a liquid metal
GB2189339A (en) * 1986-04-21 1987-10-21 Ansaldo Spa Reactor block of a fast reactor for evacuation by natural circulation of the residual power of the core
US4713213A (en) * 1984-12-18 1987-12-15 Hochtemperatur-Reaktorbau Gmbh Nuclear reactor plant housed in a steel pressure vessel with a gas cooled small high temperature reactor
US4716011A (en) * 1985-10-09 1987-12-29 Westinghouse Electric Corp. BWR fuel assembly bottom nozzle with one-way coolant flow valve
US4780270A (en) * 1986-08-13 1988-10-25 The United States Of America As Represented By The United States Department Of Energy Passive shut-down heat removal system
GB2225476A (en) * 1988-11-23 1990-05-30 Nnc Ltd Nuclear reactor
US6519308B1 (en) * 1999-06-11 2003-02-11 General Electric Company Corrosion mitigation system for liquid metal nuclear reactors with passive decay heat removal systems
US6594333B2 (en) * 2001-11-16 2003-07-15 Japan Nuclear Cycle Development Institute Thermal load reducing system for nuclear reactor vessel
CN112191287A (en) * 2020-09-30 2021-01-08 中国核动力研究设计院 Full-automatic release mechanism for high-temperature melt and control method thereof

Families Citing this family (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL7500450A (en) * 1975-01-15 1976-07-19 Neratoom NUCLEAR REACTOR INSTALLATION OF THE FAST TYPE.
US4138318A (en) * 1976-01-19 1979-02-06 Neratoom B.V. Nuclear reactor system of the fast type
FR2429478A1 (en) * 1978-06-23 1980-01-18 Commissariat Energie Atomique FAST NEUTRAL NUCLEAR BOILER WITH LIQUID METAL HEATER
FR2462002A1 (en) * 1979-07-17 1981-02-06 Commissariat Energie Atomique NUCLEAR REACTOR COOLED BY A LIQUID METAL AND PROVIDED WITH A SYSTEM FOR REMOVING THE RESIDUAL POWER
FR2500676A1 (en) * 1981-02-24 1982-08-27 Commissariat Energie Atomique EMERGENCY COOLING DEVICE FOR A WATER COOLED NUCLEAR REACTOR
FR2506498B1 (en) * 1981-05-22 1986-03-07 Commissariat Energie Atomique FAST NEUTRAL NUCLEAR REACTOR WITH RESIDUAL POWER DISCHARGE DEVICES
GB2104710A (en) * 1981-08-25 1983-03-09 Westinghouse Electric Corp Standby heat removal system for a nuclear reactor using flow diodes
FR2519462A1 (en) * 1981-12-31 1983-07-08 Novatome EMERGENCY EXHAUST DEVICE DISSIPATED BY A NUCLEAR REACTOR WITH QUICK NEUTRONS ON STOP
US4762667A (en) * 1982-12-20 1988-08-09 Westinghouse Electric Corp. Passive reactor auxiliary cooling system
FR2555794B1 (en) * 1983-11-25 1986-03-28 Commissariat Energie Atomique FAST NEUTRAL NUCLEAR REACTOR EQUIPPED WITH EMERGENCY COOLING MEANS
DE3923962A1 (en) * 1989-07-20 1991-01-31 Forschungszentrum Juelich Gmbh HIGH TEMPERATURE REACTOR
US5021211A (en) * 1989-07-25 1991-06-04 General Electric Company Liquid metal cooled nuclear reactors with passive cooling system
CN111599498B (en) * 2020-04-14 2022-11-18 中国核电工程有限公司 Passive containment air-water long-term cooling system

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1115846B (en) * 1959-06-24 1961-10-26 Babcock & Wilcox Dampfkessel Emergency cooling device for nuclear reactor plants
DE2160507C3 (en) * 1971-12-07 1975-04-30 Kernforschungsanlage Juelich Gmbh, 5170 Juelich Device for cooling the structural materials of a reactor core and for dissipating the decay heat

Cited By (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4186051A (en) * 1976-05-13 1980-01-29 Interatom, Internationale Atomreaktorbau Gmbh Nuclear energy plant with improved device for removing after-heat and emergency heat
US4115192A (en) * 1976-07-06 1978-09-19 Commissariat A L'energie Atomique Fast neutron nuclear reactor
US4342721A (en) * 1978-03-07 1982-08-03 Commissariat A L'energie Atomique Fast nuclear reactor
US4608224A (en) * 1980-07-04 1986-08-26 Service National Electricite De France Nuclear reactor cooled by a liquid metal
US4526742A (en) * 1981-03-30 1985-07-02 Ab Asea-Atom Nuclear reactor plant
GB2163890A (en) * 1984-08-29 1986-03-05 Ga Technologies Inc Nuclear reactor
US4713213A (en) * 1984-12-18 1987-12-15 Hochtemperatur-Reaktorbau Gmbh Nuclear reactor plant housed in a steel pressure vessel with a gas cooled small high temperature reactor
US4716011A (en) * 1985-10-09 1987-12-29 Westinghouse Electric Corp. BWR fuel assembly bottom nozzle with one-way coolant flow valve
GB2189339A (en) * 1986-04-21 1987-10-21 Ansaldo Spa Reactor block of a fast reactor for evacuation by natural circulation of the residual power of the core
GB2189339B (en) * 1986-04-21 1989-11-29 Ansaldo Spa Nuclear reactor.
US4780270A (en) * 1986-08-13 1988-10-25 The United States Of America As Represented By The United States Department Of Energy Passive shut-down heat removal system
GB2225476A (en) * 1988-11-23 1990-05-30 Nnc Ltd Nuclear reactor
US6519308B1 (en) * 1999-06-11 2003-02-11 General Electric Company Corrosion mitigation system for liquid metal nuclear reactors with passive decay heat removal systems
US6594333B2 (en) * 2001-11-16 2003-07-15 Japan Nuclear Cycle Development Institute Thermal load reducing system for nuclear reactor vessel
CN112191287A (en) * 2020-09-30 2021-01-08 中国核动力研究设计院 Full-automatic release mechanism for high-temperature melt and control method thereof

Also Published As

Publication number Publication date
JPS4914898A (en) 1974-02-08
FR2179839A1 (en) 1973-11-23
JPS5916238B2 (en) 1984-04-13
DE2217057C2 (en) 1982-09-09
FR2179839B3 (en) 1976-03-26
DE2217057A1 (en) 1973-10-18
IT982688B (en) 1974-10-21

Similar Documents

Publication Publication Date Title
GB1421826A (en) Convective emergency cooling systems of nuclear rectors
US20160019988A1 (en) Containment for a water cooled and moderated Nuclear Reactor
ES440763A1 (en) Integrated pressurized-water reactor and steam generator
GB1389174A (en) Nuclear reactor
US3108937A (en) Coolant-moderator circulation system for heterogeneous nuclear reactors
US3049487A (en) Direct-cycle, boiling-water nuclear reactor
US3249507A (en) Gas cooled nuclear reactor system with improved flowpath and shield arrangement
GB983742A (en) Improvements in or relating to nuclear reactor systems
FI74830B (en) KAERNREAKTOR, VARS HAERD AER AVSKAERMAD MED EN KONSTRUKTION AV STAENGER OCH TVAERSTAELLDA PLATTOR.
GB887252A (en) Improvements relating to nuclear reactors
US3251746A (en) Nuclear reactor control means
GB1291706A (en) Improvements in nuclear reactors
US3338790A (en) Fast nuclear reactor
GB1084255A (en)
US3677893A (en) Fuel assembly for a liquid-metal-cooled fast breeder reactor
US4066499A (en) Method of cooling the ceiling reflector in a nuclear reactor
US3090742A (en) Temperature control means for nuclear reactors
GB1442095A (en) Control assembly for a nuclear reactor
GB1003395A (en) Nuclear reactor
GB820579A (en) Improvements in and relating to nuclear reactors
GB943755A (en) Improvements in or relating to nuclear reactors
GB1049298A (en) Improvements in nuclear reactors
GB882714A (en) Improvements in or relating to nuclear reactors
GB1087520A (en) Nuclear reactor plants
GB1272296A (en) Nuclear reactor

Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PCNP Patent ceased through non-payment of renewal fee