GB1423069A - Nuclear reactor installations - Google Patents

Nuclear reactor installations

Info

Publication number
GB1423069A
GB1423069A GB3887073A GB3887073A GB1423069A GB 1423069 A GB1423069 A GB 1423069A GB 3887073 A GB3887073 A GB 3887073A GB 3887073 A GB3887073 A GB 3887073A GB 1423069 A GB1423069 A GB 1423069A
Authority
GB
United Kingdom
Prior art keywords
reactor
vessel
coolant
vessels
run
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
GB3887073A
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 GB1423069A publication Critical patent/GB1423069A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24Promoting flow of the coolant
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/02Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Abstract

1423069 Cooling nuclear reactors INTERATOM INTERNATIONALE ATOMREAKTORBAU GmbH 16 Aug 1973 [16 Aug 1972] 38870/73 Heading G6C In a nuclear reactor installation (e.g. employing a liquid sodium-cooled, fast reactor) heatexchangers are enclosed in secondary vessels disposed around the reactor bessel, coolant is conveyed between the reactor and secondary vessels by separate ducts forming hot and cold runs, and each secondary vessel is internally divided, by a partition, into two compartments into one of which the hot run opens and into the other of which the cold run opens, the partition affording apertures through which the heatexchangers are suspended. As shown, a cold run 10, provided by a pipe conveying coolant from the pressure side of a pump 4, leads to a core inlet plenum in reactor vessel 1 from a secondary vessel 2 housing heatexchangers 6. A hot run 12, provided by a suction pipe, leads from above the reactor core 3 to the secondary vessel 2 where the hot and cold coolant is maintained separate by a flow apron 9 through apertures of which the heat-exchangers are suspended from a respective shield plug 22. In order to compensate for thermal expansion in the pipes, each run 10, 12 extends, intermediate the vessels 1, 2, to a location above the top neutron shield 13 where the pipes are formed with loops. Gas spaces above the normal coelant levels 7, 8 in the vessels 1, 2 are connected by pressure-equalizing pipes 19. The vessels 1, 2 are surrounded by respective outer containers 17, 18 dimensioned to contain any leakage coolant and, in the instance of rupture of vessel 1, to ensure maintenance of a minimum coolant level 30 in vessel 1. Heated gas can be blown into the interspaces between vessels 1, 17 and 2, 18 for reactor start-up. To prevent all coolant from being withdrawn from vessel 1 in any circumstance, the runs 10, 12 are interconnected, in the region of the loops, by a small diameter pipe 31 which prevents siphon effects. This pipe may include a flow diode to restrict coolant by-pass flow during normal reactor operation. Inlets to the hot run 12 are disposed above the reactor vessel minimum coolant level 30.
GB3887073A 1972-08-16 1973-08-16 Nuclear reactor installations Expired GB1423069A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2240067A DE2240067C3 (en) 1972-08-16 1972-08-16 Nuclear power plant in a decentralized compact design

Publications (1)

Publication Number Publication Date
GB1423069A true GB1423069A (en) 1976-01-28

Family

ID=5853599

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3887073A Expired GB1423069A (en) 1972-08-16 1973-08-16 Nuclear reactor installations

Country Status (4)

Country Link
JP (1) JPS4946090A (en)
DE (1) DE2240067C3 (en)
FR (1) FR2196506B1 (en)
GB (1) GB1423069A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US11798697B2 (en) * 2020-08-17 2023-10-24 Terrapower, Llc Passive heat removal system for nuclear reactors

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5352896A (en) * 1976-10-22 1978-05-13 Power Reactor & Nuclear Fuel Dev Corp Liquid metal cooled nuclear reactor of cooling tank separately installed type
DE2812124A1 (en) * 1978-03-20 1979-09-27 Interatom NUCLEAR ENERGY SYSTEM IN A LOOP ARRANGEMENT
GB2090042B (en) * 1980-12-22 1984-04-26 Westinghouse Electric Corp Improved configuration for loop-type liquid metal fast breeder reactor
FR2498365B1 (en) * 1981-01-20 1986-08-29 Commissariat Energie Atomique NUCLEAR REACTOR COOLED BY A LIQUID METAL AND HAVING A THICK SLAB WITH HOUSING
DE3334821A1 (en) * 1983-09-26 1985-05-15 INTERATOM GmbH, 5060 Bergisch Gladbach CORE POWER PLANT WITH SIMPLIFIED LEAK PROTECTION OF THE COOLANT CIRCUIT
EP0349014A3 (en) * 1984-02-21 1990-07-11 Stone & Webster Engineering Corporation Support structure for a nuclear reactor

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1564054C3 (en) * 1966-12-15 1975-03-13 Gesellschaft Fuer Kernforschung Mbh, 7500 Karlsruhe Nuclear reactor
DE1815046A1 (en) * 1968-12-17 1970-06-25 Interatom Pipeline from reactor shell to heat - exchanger for a liquid cooled nuclear rct
DE2013586C3 (en) * 1970-03-21 1975-11-27 Gesellschaft Fuer Kernforschung Mbh, 7500 Karlsruhe Liquid-cooled nuclear reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US11798697B2 (en) * 2020-08-17 2023-10-24 Terrapower, Llc Passive heat removal system for nuclear reactors

Also Published As

Publication number Publication date
DE2240067B2 (en) 1981-01-29
JPS4946090A (en) 1974-05-02
DE2240067C3 (en) 1981-11-12
DE2240067A1 (en) 1974-02-28
FR2196506A1 (en) 1974-03-15
FR2196506B1 (en) 1978-07-13

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Legal Events

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