GB887252A - Improvements relating to nuclear reactors - Google Patents

Improvements relating to nuclear reactors

Info

Publication number
GB887252A
GB887252A GB2069/60A GB206960A GB887252A GB 887252 A GB887252 A GB 887252A GB 2069/60 A GB2069/60 A GB 2069/60A GB 206960 A GB206960 A GB 206960A GB 887252 A GB887252 A GB 887252A
Authority
GB
United Kingdom
Prior art keywords
reactor
cooling
convective flow
circuit
jan
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
GB2069/60A
Inventor
Thomas Deighton
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.)
Babcock International Ltd
Original Assignee
Babcock and Wilcox Ltd
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
Priority to NL121726D priority Critical patent/NL121726C/xx
Priority to NL260249D priority patent/NL260249A/xx
Application filed by Babcock and Wilcox Ltd filed Critical Babcock and Wilcox Ltd
Priority to GB2069/60A priority patent/GB887252A/en
Priority to DEB60909A priority patent/DE1156516B/en
Publication of GB887252A publication Critical patent/GB887252A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • 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
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/18—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone
    • 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

887,252. Cooling reactors. BABCOCK & WILCOX Ltd. Jan. 13, 1961 [Jan. 20, 1960], No. 2069/60. Class 39(4) [Also in Group XIII] A reactor has an emergency heat exchanger in a cooling circuit which is normally ineffective and through which convective flow is caused by expansion of liquid in the main cooling circuit of the reactor. The pressurized water reactor shown is connected by a riser 12 to an electrically heated pressurizer 13 into which water can be sprayed at 25. If cooling of the reactor by the main circuit fails, thermal expansion makes the water level 18 in the pressurizer rise until it reaches a pipe 14; convective flow can then begin in a circuit including pipes 12 and 14 and a heat exchanger 15 which loses heat to a heat sink, e.g. the sea. If the reactor is isolated by valves 20, 23, convective flow through the core can still take place by way of holes 22 or control rod channels.
GB2069/60A 1960-01-20 1960-01-20 Improvements relating to nuclear reactors Expired GB887252A (en)

Priority Applications (4)

Application Number Priority Date Filing Date Title
NL121726D NL121726C (en) 1960-01-20
NL260249D NL260249A (en) 1960-01-20
GB2069/60A GB887252A (en) 1960-01-20 1960-01-20 Improvements relating to nuclear reactors
DEB60909A DE1156516B (en) 1960-01-20 1961-01-19 Emergency cooling device for liquid-cooled nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB2069/60A GB887252A (en) 1960-01-20 1960-01-20 Improvements relating to nuclear reactors

Publications (1)

Publication Number Publication Date
GB887252A true GB887252A (en) 1962-01-17

Family

ID=9733035

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2069/60A Expired GB887252A (en) 1960-01-20 1960-01-20 Improvements relating to nuclear reactors

Country Status (3)

Country Link
DE (1) DE1156516B (en)
GB (1) GB887252A (en)
NL (2) NL121726C (en)

Cited By (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3290222A (en) * 1963-11-15 1966-12-06 Babcock & Wilcox Co Compact nuclear steam generator
US3528884A (en) * 1967-09-28 1970-09-15 Westinghouse Electric Corp Safety cooling system for a nuclear reactor
US4239596A (en) * 1977-12-16 1980-12-16 Combustion Engineering, Inc. Passive residual heat removal system for nuclear power plant
EP0026705A1 (en) * 1979-10-02 1981-04-08 COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel Emergency cooling device for a pressurized-water reactor core
FR2469779A1 (en) * 1979-11-16 1981-05-22 Commissariat Energie Atomique EMERGENCY COOLING DEVICE FOR THE HEART OF A PRESSURIZED WATER REACTOR
US4347623A (en) * 1976-05-10 1982-08-31 Reinsch A O Winfried Flash jet coolant pumping system
US4382907A (en) * 1978-06-23 1983-05-10 Commissariat A L'energie Atomique Liquid metal cooled nuclear reactor
FR2575318A1 (en) * 1984-12-24 1986-06-27 Westinghouse Electric Corp PASSIVE DEPRESSURIZATION SYSTEM FOR A NUCLEAR REACTOR
US5102616A (en) * 1988-07-21 1992-04-07 Rolls-Royce And Associates Limited Full pressure passive emergency core cooling and residual heat removal system for water cooled nuclear reactors
CN113436767A (en) * 2021-04-21 2021-09-24 广东核电合营有限公司 Nuclear reactor primary circuit hydrogen control system and method

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1489955B1 (en) * 1965-12-14 1970-05-14 Kernforschung Gmbh Ges Fuer Steam-cooled nuclear reactor
DE2446090C3 (en) * 1974-09-26 1982-03-18 Kraftwerk Union AG, 4330 Mülheim Pressurized water reactor
DE2640786A1 (en) * 1976-09-10 1978-03-16 Hochtemperatur Reaktorbau Gmbh Decay heat removal from pebble-bed nuclear reactor - uses auxiliary heat exchangers with gas flow reversed to natural convection

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1211537A (en) * 1958-08-14 1960-03-16 Commissariat Energie Atomique Heat absorption device of a nuclear reactor in the event of shutdown or overpressure

Cited By (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3290222A (en) * 1963-11-15 1966-12-06 Babcock & Wilcox Co Compact nuclear steam generator
US3528884A (en) * 1967-09-28 1970-09-15 Westinghouse Electric Corp Safety cooling system for a nuclear reactor
US4347623A (en) * 1976-05-10 1982-08-31 Reinsch A O Winfried Flash jet coolant pumping system
US4239596A (en) * 1977-12-16 1980-12-16 Combustion Engineering, Inc. Passive residual heat removal system for nuclear power plant
US4382907A (en) * 1978-06-23 1983-05-10 Commissariat A L'energie Atomique Liquid metal cooled nuclear reactor
EP0026705A1 (en) * 1979-10-02 1981-04-08 COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel Emergency cooling device for a pressurized-water reactor core
FR2466839A1 (en) * 1979-10-02 1981-04-10 Commissariat Energie Atomique HEAT-RELIEF COOLING DEVICE OF A PRESSURIZED WATER REACTOR
EP0029372A1 (en) * 1979-11-16 1981-05-27 COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel Emergency cooling system for the core of a pressurised-water nuclear reactor
FR2469779A1 (en) * 1979-11-16 1981-05-22 Commissariat Energie Atomique EMERGENCY COOLING DEVICE FOR THE HEART OF A PRESSURIZED WATER REACTOR
US4643871A (en) * 1979-11-16 1987-02-17 Commissariat A L'energie Atomique Emergency cooling device for a pressurized water reactor core
FR2575318A1 (en) * 1984-12-24 1986-06-27 Westinghouse Electric Corp PASSIVE DEPRESSURIZATION SYSTEM FOR A NUCLEAR REACTOR
US4664877A (en) * 1984-12-24 1987-05-12 Westinghouse Electric Corp. Passive depressurization system
US5102616A (en) * 1988-07-21 1992-04-07 Rolls-Royce And Associates Limited Full pressure passive emergency core cooling and residual heat removal system for water cooled nuclear reactors
CN113436767A (en) * 2021-04-21 2021-09-24 广东核电合营有限公司 Nuclear reactor primary circuit hydrogen control system and method

Also Published As

Publication number Publication date
NL121726C (en)
DE1156516B (en) 1963-10-31
NL260249A (en)

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