GB1419582A - Gas cooled fast breeder reactor installations - Google Patents

Gas cooled fast breeder reactor installations

Info

Publication number
GB1419582A
GB1419582A GB5518873A GB5518873A GB1419582A GB 1419582 A GB1419582 A GB 1419582A GB 5518873 A GB5518873 A GB 5518873A GB 5518873 A GB5518873 A GB 5518873A GB 1419582 A GB1419582 A GB 1419582A
Authority
GB
United Kingdom
Prior art keywords
steam
auxiliary
reactor
drum
pressure
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
GB5518873A
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.)
Belgonucleaire SA
Original Assignee
Belgonucleaire SA
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 Belgonucleaire SA filed Critical Belgonucleaire SA
Publication of GB1419582A publication Critical patent/GB1419582A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
    • G21C1/326—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed next to or beside the core
    • 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
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04—Reactor and engine not structurally combined
    • G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Engine Equipment That Uses Special Cycles (AREA)

Abstract

1419582 Cooling nuclear reactors BELGONUCLEAIRE SA 28 Nov 1973 [4 Dec 1972] 55188/73 Heading G6C Nuclear reactor plant includes an auxiliary heat-removal system which may operate to remove decay heat or may provide emergency cooling, the system including a turbine (disposed in a connection between a condenser and a pressure chamber which is connected to a source of steam in the reactor pressure vessel) connected to drive an auxiliary motor which may operate either an auxiliary coolant circulator or a main coolant circulator of the plant. In one embodiment, as shown, a trip or loss of fluid in the cricuit of a main turbine (not shown) leads to loss of power for the reactor coolant primary circulator motor 5, closing of valves 9, 11 in the main turbine circuit and opening of valve 13 in the live steam line whereby steam from steam generator 3 is passed to a steam drum 14. The consequent pressure increase in drum 14 gives rise to an increase in speed of water-circulating pumps 20, 21 turbines 19, 22 and alternator 23. The increased output from the latter provides an increased speed to a continuously-running pony-motor 6 to drive the reactor coolant primary circulator 4, whereby decay heat in the shut-down reactor is effectively dissipated. As the pressure in drum 14 decreases with decrease in decay heat, a heating system 15 can be operated to restore drum pressure to the level necessary for efficient operation of the abovementioned devices. In a modification (Fig. 2, not shown) the auxiliary heat removal system is connected to a steam generator (30) separate from that (3) in the main turbine circuit. A valve (35) is provided to isolate the main steam generator (3) when heat removal by the auxiliary system is required. In a second embodiment (Fig. 3, not shown) in addition to decay heat removal, the system provides for emergency cooling in the event of failure of the reactor to shut down. Three such systems are provided, each connected to two main steam-generator loops. Oil-fired auxiliary boilers 15, 57 can be operated to restore pressure in the steam drum in the circumstances set forth as under the first embodiment.
GB5518873A 1972-12-04 1973-11-28 Gas cooled fast breeder reactor installations Expired GB1419582A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
BE792257 1972-12-04

Publications (1)

Publication Number Publication Date
GB1419582A true GB1419582A (en) 1975-12-31

Family

ID=3860490

Family Applications (1)

Application Number Title Priority Date Filing Date
GB5518873A Expired GB1419582A (en) 1972-12-04 1973-11-28 Gas cooled fast breeder reactor installations

Country Status (2)

Country Link
BE (1) BE792257A (en)
GB (1) GB1419582A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0079281A1 (en) * 1981-11-05 1983-05-18 Framatome Installation comprising a pressurized water nuclear reactor with a cooling system especially suitable for the primary circuit
CN108413375A (en) * 2018-03-13 2018-08-17 中国能源建设集团广东省电力设计研究院有限公司 Emergency Cooling System and its control method for subcritical circulating fluidized bed boiler

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR3015590B1 (en) * 2013-12-19 2016-01-22 Technicatome PRIMARY PUMP OF A NUCLEAR REACTOR
CN111951993B (en) * 2020-07-23 2022-07-12 东南大学 Lead-cooled fast reactor supercritical carbon dioxide circulation switchable type vessel power system

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0079281A1 (en) * 1981-11-05 1983-05-18 Framatome Installation comprising a pressurized water nuclear reactor with a cooling system especially suitable for the primary circuit
CN108413375A (en) * 2018-03-13 2018-08-17 中国能源建设集团广东省电力设计研究院有限公司 Emergency Cooling System and its control method for subcritical circulating fluidized bed boiler
CN108413375B (en) * 2018-03-13 2019-09-13 中国能源建设集团广东省电力设计研究院有限公司 Emergency Cooling System and its control method for subcritical circulating fluidized bed boiler

Also Published As

Publication number Publication date
BE792257A (en) 1973-03-30

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee