GB1318679A – Nuclear reactor
– Google Patents
GB1318679A – Nuclear reactor
– Google Patents
Nuclear reactor
Info
Publication number
GB1318679A
GB1318679A
GB2189872A
GB2189872A
GB1318679A
GB 1318679 A
GB1318679 A
GB 1318679A
GB 2189872 A
GB2189872 A
GB 2189872A
GB 2189872 A
GB2189872 A
GB 2189872A
GB 1318679 A
GB1318679 A
GB 1318679A
Authority
GB
United Kingdom
Prior art keywords
sodium
roof
temperature
reactor
fluid
Prior art date
1971-05-24
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
GB2189872A
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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.)
1971-05-24
Filing date
1972-05-10
Publication date
1973-05-31
1972-05-10
Application filed by Commissariat a lEnergie Atomique CEA
filed
Critical
Commissariat a lEnergie Atomique CEA
1973-05-31
Publication of GB1318679A
publication
Critical
patent/GB1318679A/en
Status
Expired
legal-status
Critical
Current
Links
Espacenet
Global Dossier
Discuss
Classifications
G—PHYSICS
G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
G21C—NUCLEAR REACTORS
G21C11/00—Shielding structurally associated with the reactor
G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield Thermal insulation
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
G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
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
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
1318679 Reactors COMMISSARIAT A L’ENERGIE ATOMIQUE 10 May 1972 [24 May 1971] 21898/72 Heading G6C In a sodium-cooled, fast, integral nuclear reactor, the pressure vessel roof is maintained at a temperature sufficient to prevent mechanical stresses in the roof due to high temperature gradients. Liquid sodium (or sodium-potassium eutectic) flows in the pipe circuit, 6, so as to maintain reactor vessel roof, 3, and the same temperature as the reactor sodium coolant, 4. The fluid in the vertical section of 6, within 4, is brought to the temperature of 4 before passing to the horizontal section upon the roof 3. The fluid may flow to the pipes 6 from the collectors 7, 8 either by natural convection or by means of the pump, 14. The coolant circuit 6 can be used also for removing shut-down heat or for emergency cooling.
GB2189872A
1971-05-24
1972-05-10
Nuclear reactor
Expired
GB1318679A
(en)
Applications Claiming Priority (1)
Application Number
Priority Date
Filing Date
Title
FR7118628A
FR2138327B1
(en)
1971-05-24
1971-05-24
Publications (1)
Publication Number
Publication Date
GB1318679A
true
GB1318679A
(en)
1973-05-31
Family
ID=9077481
Family Applications (1)
Application Number
Title
Priority Date
Filing Date
GB2189872A
Expired
GB1318679A
(en)
1971-05-24
1972-05-10
Nuclear reactor
Country Status (7)
Country
Link
US
(1)
US3830695A
(en)
BE
(1)
BE783345A
(en)
CH
(1)
CH556593A
(en)
ES
(1)
ES403085A1
(en)
FR
(1)
FR2138327B1
(en)
GB
(1)
GB1318679A
(en)
IT
(1)
IT958948B
(en)
Families Citing this family (12)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
GB1476632A
(en)
*
1973-07-17
1977-06-16
Foster Wheeler Power Prod
Steam generating plant
GB1450203A
(en)
*
1973-09-28
1976-09-22
Atomic Energy Authority Uk
Nuclear reactor containments
JPS5149393A
(en)
*
1974-08-30
1976-04-28
Commissariat Energie Atomique
FR2283517A1
(en)
*
1974-08-30
1976-03-26
Commissariat Energie Atomique
THERMAL PROTECTION DEVICE FOR THE TANK OF A QUICK NEUTRON NUCLEAR REACTOR
DE2623978C2
(en)
*
1976-05-28
1986-12-11
GHT Gesellschaft für Hochtemperaturreaktor-Technik mbH, 5060 Bergisch Gladbach
High-temperature nuclear reactor with residual heat dissipation via the ceiling reflector
US4235284A
(en)
*
1976-12-16
1980-11-25
The United States Of America As Represented By The United States Department Of Energy
Heat exchanger with auxiliary cooling system
DE3009390A1
(en)
*
1980-03-12
1981-09-17
GHT Gesellschaft für Hochtemperaturreaktor-Technik mbH, 5060 Bergisch Gladbach
HIGH TEMPERATURE REACTOR
FR2486296B1
(en)
*
1980-07-04
1986-06-06
Electricite De France
NUCLEAR REACTOR COOLED BY LIQUID METAL
FR2495815B1
(en)
*
1980-12-09
1986-09-19
Commissariat Energie Atomique
NUCLEAR REACTOR COOLED BY A LIQUID METAL CONTAINED IN A TANK CLOSED BY SUPERIOR CLOSURES
US4508677A
(en)
*
1983-02-09
1985-04-02
General Electric Company
Modular nuclear reactor for a land-based power plant and method for the fabrication, installation and operation thereof
GB2157059B
(en)
*
1984-04-06
1988-03-16
Nat Nuclear Corp Ltd
Improvements in nuclear reactors
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
Family Cites Families (5)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
GB955844A
(en)
*
1962-03-02
BE633085A
(en)
*
1962-05-30
GB983379A
(en)
*
1963-02-12
1965-02-17
Atomic Energy Authority Uk
Improvements in or relating to concrete pressure vessels
US3548931A
(en)
*
1968-10-30
1970-12-22
Atomic Energy Commission
Vessel for a sodium-cooled reactor
CH511498A
(en)
*
1969-03-10
1971-08-15
Commissariat Energie Atomique
Thermal protection device for the vessel of a nuclear reactor
1971
1971-05-24
FR
FR7118628A
patent/FR2138327B1/fr
not_active
Expired
1972
1972-05-10
CH
CH700372A
patent/CH556593A/en
not_active
IP Right Cessation
1972-05-10
GB
GB2189872A
patent/GB1318679A/en
not_active
Expired
1972-05-12
BE
BE783345A
patent/BE783345A/en
unknown
1972-05-15
US
US00253021A
patent/US3830695A/en
not_active
Expired – Lifetime
1972-05-23
ES
ES403085A
patent/ES403085A1/en
not_active
Expired
1972-05-23
IT
IT68628/72A
patent/IT958948B/en
active
Also Published As
Publication number
Publication date
BE783345A
(en)
1972-09-01
FR2138327A1
(en)
1973-01-05
US3830695A
(en)
1974-08-20
IT958948B
(en)
1973-10-30
FR2138327B1
(en)
1974-03-08
ES403085A1
(en)
1977-07-16
CH556593A
(en)
1974-11-29
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Legal Events
Date
Code
Title
Description
1973-10-10
PS
Patent sealed [section 19, patents act 1949]
1976-10-20
435
Patent endorsed ‘licences of right’ on the date specified (sect. 35/1949)
1982-12-08
PCNP
Patent ceased through non-payment of renewal fee
