FR2296248A1 - Nuclear reactor fuelled by eutectic salt mixture - with integral primary cooling system - Google Patents

Nuclear reactor fuelled by eutectic salt mixture - with integral primary cooling system

Info

Publication number
FR2296248A1
FR2296248A1 FR7442767A FR7442767A FR2296248A1 FR 2296248 A1 FR2296248 A1 FR 2296248A1 FR 7442767 A FR7442767 A FR 7442767A FR 7442767 A FR7442767 A FR 7442767A FR 2296248 A1 FR2296248 A1 FR 2296248A1
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
FR7442767A
Other languages
French (fr)
Other versions
FR2296248B1 (en
Inventor
Michel Grenon
Edmond Ventre
Jacques Marcel Blum
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 FR7442767A priority Critical patent/FR2296248A1/en
Priority to BE162646A priority patent/BE836523A/en
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/en
Publication of FR2296248A1 publication Critical patent/FR2296248A1/en
Application granted granted Critical
Publication of FR2296248B1 publication Critical patent/FR2296248B1/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
    • G21C1/04—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
    • G21C15/24—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)

Abstract

In a nuclear reactor fuelled by molten salt. The reactor vessel is a double-walled vessel housing the reactor core of graphite suitably pierced with channels for the circulation of the molten fissile material, e.g. uranium fluoride/lithium fluoride eutectic mixt. Fissile material circulates upwards through the core and out via passages to a series of heat exchanger which discharge cooled liquid via outlet channels to a series of circulating pumps which return the liquid back to the core. Heat is extracted by pumping a suitable coolant through heat exchangers. As the corrosive props. of the fissile material are greatest at high temp., the path of hot material from the reactor core to the heat exchangers, is therefore kept as short as possible. The volume of fissile material in circulation is minimised; corrosion is kept to a minimum by the location of primary cooling equipment inside the reactor vessel.
FR7442767A 1974-12-24 1974-12-24 Nuclear reactor fuelled by eutectic salt mixture - with integral primary cooling system Granted FR2296248A1 (en)

Priority Applications (6)

Application Number Priority Date Filing Date Title
FR7442767A FR2296248A1 (en) 1974-12-24 1974-12-24 Nuclear reactor fuelled by eutectic salt mixture - with integral primary cooling system
BE162646A BE836523A (en) 1974-12-24 1975-12-11 MELTED FUEL SALT NUCLEAR REACTOR
GB51485/75A GB1494055A (en) 1974-12-24 1975-12-16 Molten salt in a nuclear reactor
CH1644875A CH596639A5 (en) 1974-12-24 1975-12-18
US05/642,996 US4045286A (en) 1974-12-24 1975-12-22 Molten fuel-salt reactor
DE2558179A DE2558179C3 (en) 1974-12-24 1975-12-23 Molten salt nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7442767A FR2296248A1 (en) 1974-12-24 1974-12-24 Nuclear reactor fuelled by eutectic salt mixture - with integral primary cooling system

Publications (2)

Publication Number Publication Date
FR2296248A1 true FR2296248A1 (en) 1976-07-23
FR2296248B1 FR2296248B1 (en) 1977-11-10

Family

ID=9146600

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7442767A Granted FR2296248A1 (en) 1974-12-24 1974-12-24 Nuclear reactor fuelled by eutectic salt mixture - with integral primary cooling system

Country Status (2)

Country Link
BE (1) BE836523A (en)
FR (1) FR2296248A1 (en)

Cited By (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4183785A (en) * 1975-06-26 1980-01-15 Electricite de France (Service National) Pechiney Ugine-Kuhlmann Method for positioning moderator structure for the core of a molten-salt reactor
FR2480482A1 (en) * 1980-04-15 1981-10-16 Kazuo Furukawa SINGLE FLUID TYPE ACCELERATOR SALT SURFERATOR
NL2000078C2 (en) * 2006-05-19 2007-11-20 Gerrit Clemens Van Uitert Nuclear reactor.
WO2017192463A3 (en) * 2016-05-02 2018-03-01 Terrapower, Llc Improved molten fuel reactor thermal management configurations
CZ308183B6 (en) * 2017-11-29 2020-02-12 Centrum Výzkumu Řež S.R.O. High temperature nuclear reactor, cooled by molten fluoride salt
US10665356B2 (en) 2015-09-30 2020-05-26 Terrapower, Llc Molten fuel nuclear reactor with neutron reflecting coolant
US10734122B2 (en) 2015-09-30 2020-08-04 Terrapower, Llc Neutron reflector assembly for dynamic spectrum shifting
US10867710B2 (en) 2015-09-30 2020-12-15 Terrapower, Llc Molten fuel nuclear reactor with neutron reflecting coolant
US10923238B2 (en) 2016-11-15 2021-02-16 Terrapower, Llc Direct reactor auxiliary cooling system for a molten salt nuclear reactor
US11075015B2 (en) 2018-03-12 2021-07-27 Terrapower, Llc Reflectors for molten chloride fast reactors
US11075013B2 (en) 2016-07-15 2021-07-27 Terrapower, Llc Removing heat from a nuclear reactor by having molten fuel pass through plural heat exchangers before returning to core
US11145424B2 (en) 2018-01-31 2021-10-12 Terrapower, Llc Direct heat exchanger for molten chloride fast reactor
US11170901B2 (en) 2014-12-29 2021-11-09 Terrapower, Llc Fission reaction control in a molten salt reactor
US11276503B2 (en) 2014-12-29 2022-03-15 Terrapower, Llc Anti-proliferation safeguards for nuclear fuel salts
US11373765B2 (en) 2016-08-10 2022-06-28 Terrapower, Llc Electro-synthesis of uranium chloride fuel salts
US11728052B2 (en) 2020-08-17 2023-08-15 Terra Power, Llc Fast spectrum molten chloride test reactors
US11881320B2 (en) 2019-12-23 2024-01-23 Terrapower, Llc Molten fuel reactors and orifice ring plates for molten fuel reactors
US12049408B2 (en) 2018-09-14 2024-07-30 Terrapower, Llc Corrosion-resistant coolant salt and method for making same

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110110392B (en) * 2019-04-17 2021-02-12 华南理工大学 Reactor core parameter calculation method of molten salt reactor with silicon carbide as moderator

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2810689A (en) * 1945-11-06 1957-10-22 Eugene P Wigner Fluid moderated reactor
FR2002531A1 (en) * 1968-02-23 1969-10-17 Atomic Energy Authority Uk NUCLEAR REACTOR COOLED BY A LIQUID LIKELY TO SOLIDIFY IN WHICH THE HEART IS IMMERSED
DE1564994A1 (en) * 1966-09-27 1970-01-08 Atomic Energy Authority Uk Nuclear reactor

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2810689A (en) * 1945-11-06 1957-10-22 Eugene P Wigner Fluid moderated reactor
DE1564994A1 (en) * 1966-09-27 1970-01-08 Atomic Energy Authority Uk Nuclear reactor
FR2002531A1 (en) * 1968-02-23 1969-10-17 Atomic Energy Authority Uk NUCLEAR REACTOR COOLED BY A LIQUID LIKELY TO SOLIDIFY IN WHICH THE HEART IS IMMERSED

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
REVUE US: TRANSACTIONS OF THE ASME-JOURNAL OF ENGINEERING FOR POWER, SERIES A, VOL. 88, OCTOBRE 1966, PAGES 355-366, "A POTASSIUM-STEAM BINARY VAPOR CYCLE FOR A MOLTEN-SALT REACTOR POWER PLANT", PAR A.P. FRAAS *

Cited By (29)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4183785A (en) * 1975-06-26 1980-01-15 Electricite de France (Service National) Pechiney Ugine-Kuhlmann Method for positioning moderator structure for the core of a molten-salt reactor
FR2480482A1 (en) * 1980-04-15 1981-10-16 Kazuo Furukawa SINGLE FLUID TYPE ACCELERATOR SALT SURFERATOR
NL2000078C2 (en) * 2006-05-19 2007-11-20 Gerrit Clemens Van Uitert Nuclear reactor.
US11276503B2 (en) 2014-12-29 2022-03-15 Terrapower, Llc Anti-proliferation safeguards for nuclear fuel salts
US11170901B2 (en) 2014-12-29 2021-11-09 Terrapower, Llc Fission reaction control in a molten salt reactor
US10734122B2 (en) 2015-09-30 2020-08-04 Terrapower, Llc Neutron reflector assembly for dynamic spectrum shifting
US10665356B2 (en) 2015-09-30 2020-05-26 Terrapower, Llc Molten fuel nuclear reactor with neutron reflecting coolant
US11798694B2 (en) 2015-09-30 2023-10-24 Terrapower, Llc Molten fuel nuclear reactor
US10867710B2 (en) 2015-09-30 2020-12-15 Terrapower, Llc Molten fuel nuclear reactor with neutron reflecting coolant
US10741293B2 (en) 2016-05-02 2020-08-11 Terrapower, Llc Molten fuel reactor cooling and pump configurations
KR20220038532A (en) * 2016-05-02 2022-03-28 테라파워, 엘엘씨 Improved molten fuel reactor thermal management configurations
AU2021277692B2 (en) * 2016-05-02 2023-03-16 Terrapower, Llc Improved molten fuel reactor thermal management configurations
EA035652B1 (en) * 2016-05-02 2020-07-22 ТерраПауэр, ЭлЭлСи Improved molten fuel nuclear reactor thermal management configuration
US11367536B2 (en) 2016-05-02 2022-06-21 Terrapower, Llc Molten fuel reactor thermal management configurations
KR20190004751A (en) * 2016-05-02 2019-01-14 테라파워, 엘엘씨 Improved Melt-Fuel Reactor Thermal Management Configuration
AU2017261230B2 (en) * 2016-05-02 2022-02-24 Terrapower, Llc Improved molten fuel reactor thermal management configurations
WO2017192463A3 (en) * 2016-05-02 2018-03-01 Terrapower, Llc Improved molten fuel reactor thermal management configurations
KR102377348B1 (en) * 2016-05-02 2022-03-22 테라파워, 엘엘씨 Improved molten fuel reactor thermal management configuration
US11075013B2 (en) 2016-07-15 2021-07-27 Terrapower, Llc Removing heat from a nuclear reactor by having molten fuel pass through plural heat exchangers before returning to core
US11373765B2 (en) 2016-08-10 2022-06-28 Terrapower, Llc Electro-synthesis of uranium chloride fuel salts
US11488731B2 (en) 2016-11-15 2022-11-01 Terrapower, Llc Direct reactor auxiliary cooling system for a molten salt nuclear reactor
US10923238B2 (en) 2016-11-15 2021-02-16 Terrapower, Llc Direct reactor auxiliary cooling system for a molten salt nuclear reactor
CZ308183B6 (en) * 2017-11-29 2020-02-12 Centrum Výzkumu Řež S.R.O. High temperature nuclear reactor, cooled by molten fluoride salt
US11145424B2 (en) 2018-01-31 2021-10-12 Terrapower, Llc Direct heat exchanger for molten chloride fast reactor
US11075015B2 (en) 2018-03-12 2021-07-27 Terrapower, Llc Reflectors for molten chloride fast reactors
US11791057B2 (en) 2018-03-12 2023-10-17 Terrapower, Llc Reflectors for molten chloride fast reactors
US12049408B2 (en) 2018-09-14 2024-07-30 Terrapower, Llc Corrosion-resistant coolant salt and method for making same
US11881320B2 (en) 2019-12-23 2024-01-23 Terrapower, Llc Molten fuel reactors and orifice ring plates for molten fuel reactors
US11728052B2 (en) 2020-08-17 2023-08-15 Terra Power, Llc Fast spectrum molten chloride test reactors

Also Published As

Publication number Publication date
FR2296248B1 (en) 1977-11-10
BE836523A (en) 1976-04-01

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ST Notification of lapse