BE836523A - MELTED FUEL SALT NUCLEAR REACTOR - Google Patents

MELTED FUEL SALT NUCLEAR REACTOR

Info

Publication number
BE836523A
BE836523A BE162646A BE162646A BE836523A BE 836523 A BE836523 A BE 836523A BE 162646 A BE162646 A BE 162646A BE 162646 A BE162646 A BE 162646A BE 836523 A BE836523 A BE 836523A
Authority
BE
Belgium
Prior art keywords
nuclear reactor
fuel salt
salt nuclear
melted fuel
melted
Prior art date
Application number
BE162646A
Other languages
French (fr)
Inventor
J-M Blum
M Grenon
E Ventre
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 filed Critical
Publication of BE836523A publication Critical patent/BE836523A/en

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)
BE162646A 1974-12-24 1975-12-11 MELTED FUEL SALT NUCLEAR REACTOR BE836523A (en)

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 (1)

Publication Number Publication Date
BE836523A true BE836523A (en) 1976-04-01

Family

ID=9146600

Family Applications (1)

Application Number Title Priority Date Filing Date
BE162646A BE836523A (en) 1974-12-24 1975-12-11 MELTED FUEL SALT NUCLEAR REACTOR

Country Status (2)

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

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110110392A (en) * 2019-04-17 2019-08-09 华南理工大学 It is a kind of using silicon carbide as the reactor core calculation method of parameters of the molten salt reactor of moderator

Families Citing this family (17)

* 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
CA1183287A (en) * 1980-04-15 1985-02-26 Kazuo Furukawa Single fluid type accelerator molten-salt breeder
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
JP2018507396A (en) 2014-12-29 2018-03-15 テラパワー， エルエルシー Nuclear material processing
CA2999894A1 (en) 2015-09-30 2017-04-06 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
US10867710B2 (en) 2015-09-30 2020-12-15 Terrapower, Llc Molten fuel nuclear reactor with neutron reflecting coolant
CA3018444C (en) * 2016-05-02 2021-07-06 Terrapower, Llc Improved molten fuel reactor cooling and pump configurations
EP3485496B1 (en) 2016-07-15 2020-04-15 TerraPower, LLC Vertically-segmented nuclear reactor
EP3922605A1 (en) 2016-08-10 2021-12-15 TerraPower LLC Electro-synthesis of uranium chloride fuel salts
EP3542371B1 (en) 2016-11-15 2021-03-03 TerraPower, LLC Thermal management of molten fuel nuclear reactors
CZ308183B6 (en) * 2017-11-29 2020-02-12 Centrum Výzkumu Řež S.R.O. High temperature nuclear reactor, cooled by molten fluoride salt
WO2019152595A1 (en) 2018-01-31 2019-08-08 Terrapower, Llc Direct heat exchanger for molten chloride fast reactor
EP4297043A3 (en) 2018-03-12 2024-06-12 TerraPower LLC Reflector assembly for a molten chloride fast reactor
JP2023508951A (en) 2019-12-23 2023-03-06 テラパワー， エルエルシー Orifice ring plate for molten fuel reactors and molten fuel reactors
US11728052B2 (en) 2020-08-17 2023-08-15 Terra Power, Llc Fast spectrum molten chloride test reactors

Family Cites Families (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
DE1564994B2 (en) * 1966-09-27 1977-06-08 United Kingdom Atomic Energy Authority, London CORE OF A NUCLEAR REACTOR
GB1256874A (en) * 1968-02-23 1971-12-15

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110110392A (en) * 2019-04-17 2019-08-09 华南理工大学 It is a kind of using silicon carbide as the reactor core calculation method of parameters of the molten salt reactor of moderator
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

Also Published As

Publication number Publication date
FR2296248A1 (en) 1976-07-23
FR2296248B1 (en) 1977-11-10

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