GB1249331A – Improvements in or relating to liquid metal cooled fast breeder nuclear reactors
– Google Patents
GB1249331A – Improvements in or relating to liquid metal cooled fast breeder nuclear reactors
– Google Patents
Improvements in or relating to liquid metal cooled fast breeder nuclear reactors
Info
Publication number
GB1249331A
GB1249331A
GB8535/68A
GB853568A
GB1249331A
GB 1249331 A
GB1249331 A
GB 1249331A
GB 8535/68 A
GB8535/68 A
GB 8535/68A
GB 853568 A
GB853568 A
GB 853568A
GB 1249331 A
GB1249331 A
GB 1249331A
Authority
GB
United Kingdom
Prior art keywords
shield
sodium
core
ducts
fuel
Prior art date
1968-01-30
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
GB8535/68A
Inventor
George Oliver Jackson
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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.)
1968-01-30
Filing date
1968-01-30
Publication date
1971-10-13
1968-01-30
Application filed by UK Atomic Energy Authority
filed
Critical
UK Atomic Energy Authority
1969-01-13
Priority to US00790779A
priority
Critical
patent/US3715270A/en
1969-01-29
Priority to DE1904200A
priority
patent/DE1904200C3/en
1969-01-29
Priority to JP44006587A
priority
patent/JPS4840280B1/ja
1969-01-29
Priority to ES363057A
priority
patent/ES363057A1/en
1969-01-29
Priority to FR696901789A
priority
patent/FR2000967B1/fr
1969-01-29
Priority to SE01188/69A
priority
patent/SE350139B/xx
1969-01-30
Priority to BE727691D
priority
patent/BE727691A/xx
1971-10-13
Publication of GB1249331A
publication
Critical
patent/GB1249331A/en
Status
Expired
legal-status
Critical
Current
Links
Espacenet
Global Dossier
Discuss
Classifications
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
Abstract
1,249,331. Fast reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. 9 Jan., 1969 [30 Jan., 1968; 21 Feb., 1968], Nos. 4847/68 and 8535/68. Heading G6C. A large power-producing fast breeder reactor comprises a sodium-filled tank 1 within a vault 2 closed by a roof 3. The sodium level is denoted by chain-line L and disposed in the sodium are the reactor core 4, four primary heat exchangers 6, four sodium-coolant pumps 7 and interconnecting ducts 15, 16, 17. The core 4 is disposed in an open-topped vessel 50 having thermal insulation 9 and neutron shielding 10 and closed by a lid 11 having neutron shielding 22. A platform 12 constituting the bottom of the vessel 50 is supported by beams 13 suspended by a cylinder 14 from the roof 3, the lid 11 being suspended by a pillar 44. The ducts 15 penetrate the side wall 8 of the vessel 50 and conduct hot coolant from the upper region of the core to the heat exchangers 6. The ducts 16 lead the coolant from the exchangers 6, to the inlet of pumps 7, the coolant being returned to the lower end of the core by the ducts 17. The ducts 17 extend through platform 12 and terminate at a junction with the inlet ends of fuel element support tubes (not shown) carried by the diagrid 18. Leakage or flow-back of sodium from the junction mentioned above collects in a tank 20 and is returned by ducts 21 to a pump 7. Additionally, (not shown) the ducts 21 can be branched to the upper end of the core to scavenge cool sodium from the sodium pool in the tank which may otherwise be able to leak through the lid 11. A fuel store 24 for irradiated fuel sub-assemblies 27 has thermal insulation 26 and is disposed adjacent the vessel 50, these subassemblies being cooled by convection flow of sodium in the pool. The fuel sub-assemblies are transferred from the core 4 to the store 24 by tubes 23 provided at their upper ends with transfer machines (not shown), the upper ends of the pipes terminating in a rotatable inner shield 32. The inner shield 32 is eccentrically mounted in an outer rotatable shield 33 and the axis of the shield 32 may be aligned with the axis of the core 4. A refuelling machine 31 on the outer shield 33 may be connected at its upper end to a flask (not shown) whereby new fuel sub-assemblies may be loaded into the store 24 and irradiated fuel sub-assemblies may be removed to a remote facility. The inner shield 32 also supports the lid 11 through the pillar 44 and carries equipment 36 for operating the control elements 37. Further equipment 41, 42 43 carried by the shield 32 serves to monitor the coolant and measure the fuel temperature. Jacking means (not shown) are provided for lifting the shield 32 relatively to the shield 33 prior to rotation of the shield 32 or 33. In a modification described with reference to Figs. 3-5 (not shown) the tank 1 is elliptical in plan view, the reactor core being situated at the centre of the major axis but displaced off-centre on the minor axis to provide space for the fuel store. The space at each end of the ellipse is occupied by the primary heat exchangers and pumps.
GB8535/68A
1968-01-30
1968-01-30
Improvements in or relating to liquid metal cooled fast breeder nuclear reactors
Expired
GB1249331A
(en)
Priority Applications (7)
Application Number
Priority Date
Filing Date
Title
US00790779A
US3715270A
(en)
1968-01-30
1969-01-13
Nuclear reactors
DE1904200A
DE1904200C3
(en)
1968-01-30
1969-01-29
Fast power breeder reactor cooled with liquid metal
JP44006587A
JPS4840280B1
(en)
1968-01-30
1969-01-29
ES363057A
ES363057A1
(en)
1968-01-30
1969-01-29
Nuclear reactors
FR696901789A
FR2000967B1
(en)
1968-01-30
1969-01-29
SE01188/69A
SE350139B
(en)
1968-01-30
1969-01-29
BE727691D
BE727691A
(en)
1968-01-30
1969-01-30
Applications Claiming Priority (1)
Application Number
Priority Date
Filing Date
Title
GB484768
1968-01-30
Publications (1)
Publication Number
Publication Date
GB1249331A
true
GB1249331A
(en)
1971-10-13
Family
ID=9784919
Family Applications (1)
Application Number
Title
Priority Date
Filing Date
GB8535/68A
Expired
GB1249331A
(en)
1968-01-30
1968-01-30
Improvements in or relating to liquid metal cooled fast breeder nuclear reactors
Country Status (1)
Country
Link
GB
(1)
GB1249331A
(en)
Cited By (4)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
US4331512A
(en)
*
1979-04-23
1982-05-25
Electric Power Research Institute, Inc.
Nuclear reactor guard vessel arrangement
US4336614A
(en)
*
1978-09-19
1982-06-22
Nuclear Power Company Limited
Tube-in-shell heat exchangers
CN113130096A
(en)
*
2021-03-05
2021-07-16
安徽中科超核科技有限公司
Liquid metal reactor for vehicle-mounted transportation
CN116052909A
(en)
*
2022-12-26
2023-05-02
中国原子能科学研究院
Reactor vessel
1968
1968-01-30
GB
GB8535/68A
patent/GB1249331A/en
not_active
Expired
Cited By (6)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
US4336614A
(en)
*
1978-09-19
1982-06-22
Nuclear Power Company Limited
Tube-in-shell heat exchangers
US4331512A
(en)
*
1979-04-23
1982-05-25
Electric Power Research Institute, Inc.
Nuclear reactor guard vessel arrangement
CN113130096A
(en)
*
2021-03-05
2021-07-16
安徽中科超核科技有限公司
Liquid metal reactor for vehicle-mounted transportation
CN113130096B
(en)
*
2021-03-05
2022-07-19
安徽中科超核科技有限公司
Liquid metal reactor for vehicle-mounted transportation
CN116052909A
(en)
*
2022-12-26
2023-05-02
中国原子能科学研究院
Reactor vessel
CN116052909B
(en)
*
2022-12-26
2023-10-27
中国原子能科学研究院
Reactor vessel
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