FR2331863A2 - Reacteur nucleaire a sel combustible fondu - Google Patents

Reacteur nucleaire a sel combustible fondu

Info

Publication number
FR2331863A2
FR2331863A2 FR7535055A FR7535055A FR2331863A2 FR 2331863 A2 FR2331863 A2 FR 2331863A2 FR 7535055 A FR7535055 A FR 7535055A FR 7535055 A FR7535055 A FR 7535055A FR 2331863 A2 FR2331863 A2 FR 2331863A2
Authority
FR
France
Prior art keywords
core
reactor
fissile material
fuelled
primary cooling
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.)
Granted
Application number
FR7535055A
Other languages
English (en)
Other versions
FR2331863B2 (fr
Inventor
Jacques Marcel Blum
Michel Grenon
Edmond Ventre
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.)
Electricite de France SA
Original Assignee
Electricite de France 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 Electricite de France SA filed Critical Electricite de France SA
Priority to FR7535055A priority Critical patent/FR2331863A2/fr
Priority to GB51485/75A priority patent/GB1494055A/en
Priority to CH1644875A priority patent/CH596639A5/xx
Priority to US05/642,996 priority patent/US4045286A/en
Priority to DE2558179A priority patent/DE2558179C3/de
Publication of FR2331863A2 publication Critical patent/FR2331863A2/fr
Application granted granted Critical
Publication of FR2331863B2 publication Critical patent/FR2331863B2/fr
Granted 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
    • 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
    • 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
    • G21C1/22—Heterogeneous reactors, i.e. in which fuel and moderator are separated using liquid or gaseous fuel
    • 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
    • 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
    • G21C15/24—Promoting flow of the 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
    • 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
FR7535055A 1974-12-24 1975-11-17 Reacteur nucleaire a sel combustible fondu Granted FR2331863A2 (fr)

Priority Applications (5)

Application Number Priority Date Filing Date Title
FR7535055A FR2331863A2 (fr) 1975-11-17 1975-11-17 Reacteur nucleaire a sel combustible fondu
GB51485/75A GB1494055A (en) 1974-12-24 1975-12-16 Molten salt in a nuclear reactor
CH1644875A CH596639A5 (fr) 1974-12-24 1975-12-18
US05/642,996 US4045286A (en) 1974-12-24 1975-12-22 Molten fuel-salt reactor
DE2558179A DE2558179C3 (de) 1974-12-24 1975-12-23 Salzschmelzen-Kernreaktor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7535055A FR2331863A2 (fr) 1975-11-17 1975-11-17 Reacteur nucleaire a sel combustible fondu

Publications (2)

Publication Number Publication Date
FR2331863A2 true FR2331863A2 (fr) 1977-06-10
FR2331863B2 FR2331863B2 (fr) 1979-07-13

Family

ID=9162507

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7535055A Granted FR2331863A2 (fr) 1974-12-24 1975-11-17 Reacteur nucleaire a sel combustible fondu

Country Status (1)

Country Link
FR (1) FR2331863A2 (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1987007695A1 (fr) * 1986-06-16 1987-12-17 Le Carbone Lorraine Contact thermique a fort coefficient de transfert et applications au refroidissement d'une structure soumise a un flux thermique intense

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1987007695A1 (fr) * 1986-06-16 1987-12-17 Le Carbone Lorraine Contact thermique a fort coefficient de transfert et applications au refroidissement d'une structure soumise a un flux thermique intense
EP0250345A1 (fr) * 1986-06-16 1987-12-23 Le Carbone Lorraine Contact thermique à fort coefficient de transfert et applications au refroidissement d'une structure soumise à un flux thermique intense
US4852645A (en) * 1986-06-16 1989-08-01 Le Carbone Lorraine Thermal transfer layer

Also Published As

Publication number Publication date
FR2331863B2 (fr) 1979-07-13

Similar Documents

Publication Publication Date Title
FR2296248A1 (fr) Reacteur nucleaire a sel combustible fondu
GB835266A (en) Improvements relating to nuclear reactors
GB1343639A (en) Liquid cooled nuclear reactor
GB1494055A (en) Molten salt in a nuclear reactor
GB1135974A (en) Liquid-cooled nuclear reactor
GB1210048A (en) Vessel for a sodium-cooled reactor
GB827085A (en) Nuclear reactors
ES8103871A1 (es) Perfeccionamientos en circuitos caloportadores secundarios para reactores nucleares
GB916064A (en) Shipping container for spent nuclear reactor fuel elements
GB1402213A (en) Nuclear reactor
GB1128913A (en) Nuclear reactors
FR2331863A2 (fr) Reacteur nucleaire a sel combustible fondu
GB1335528A (en) Pressure vessel
GB1166569A (en) Improvements in or relating to Nuclear Reactors
GB1214439A (en) Thermal shield system for a nuclear reactor vessel
JPH04216492A (ja) 深海調査船用原子炉
GB1247897A (en) Nuclear reactor pressure vessels
GB1283010A (en) Heat exchanger apparatus
GB1101067A (en) Improvements in or relating to metal-lined concrete pressure vessels
GB1336716A (en) Emergency cooling system for a nuclear reactor
FR2265152A1 (en) Pressure water nuclear reactor - with external heat exchangers and pumps for use as steam generator on a ship
GB1137298A (en) Improvements in and relating to a nuclear installation
GB1049298A (en) Improvements in nuclear reactors
GB1207120A (en) Improvements in and relating to nuclear reactors
FR2282698A2 (fr) Chaudiere nucleaire