FR1363360A - Improvement of the primary circuit of power reactors cooled by liquid sodium - Google Patents

Improvement of the primary circuit of power reactors cooled by liquid sodium

Info

Publication number
FR1363360A
FR1363360A FR933347A FR933347A FR1363360A FR 1363360 A FR1363360 A FR 1363360A FR 933347 A FR933347 A FR 933347A FR 933347 A FR933347 A FR 933347A FR 1363360 A FR1363360 A FR 1363360A
Authority
FR
France
Prior art keywords
improvement
primary circuit
liquid sodium
power reactors
reactors cooled
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.)
Expired
Application number
FR933347A
Other languages
French (fr)
Inventor
Roger Devidas
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.)
Groupement Atomique Alsacienne Atlantique SA
Alsacienne Atom
Original Assignee
Groupement Atomique Alsacienne Atlantique SA
Alsacienne Atom
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 Groupement Atomique Alsacienne Atlantique SA, Alsacienne Atom filed Critical Groupement Atomique Alsacienne Atlantique SA
Priority to FR933347A priority Critical patent/FR1363360A/en
Priority to BE647227A priority patent/BE647227A/xx
Priority to GB17576/64A priority patent/GB1005489A/en
Priority to DEG40491A priority patent/DE1209579B/en
Application granted granted Critical
Publication of FR1363360A publication Critical patent/FR1363360A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04—Reactor and engine not structurally combined
    • G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
    • 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
    • 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
    • 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
    • G21C15/243—Promoting flow of the coolant for liquids
    • G21C15/247—Promoting flow of the coolant for liquids for liquid metals
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G21C5/08—Means for preventing undesired asymmetric expansion of the complete structure ; Stretching devices, pins
    • 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
    • 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)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
FR933347A 1963-04-30 1963-04-30 Improvement of the primary circuit of power reactors cooled by liquid sodium Expired FR1363360A (en)

Priority Applications (4)

Application Number Priority Date Filing Date Title
FR933347A FR1363360A (en) 1963-04-30 1963-04-30 Improvement of the primary circuit of power reactors cooled by liquid sodium
BE647227A BE647227A (en) 1963-04-30 1964-04-28
GB17576/64A GB1005489A (en) 1963-04-30 1964-04-28 Cooling apparatus for a nuclear reactor
DEG40491A DE1209579B (en) 1963-04-30 1964-04-29 Arrangement for cooling a nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR933347A FR1363360A (en) 1963-04-30 1963-04-30 Improvement of the primary circuit of power reactors cooled by liquid sodium

Publications (1)

Publication Number Publication Date
FR1363360A true FR1363360A (en) 1964-06-12

Family

ID=8802844

Family Applications (1)

Application Number Title Priority Date Filing Date
FR933347A Expired FR1363360A (en) 1963-04-30 1963-04-30 Improvement of the primary circuit of power reactors cooled by liquid sodium

Country Status (4)

Country Link
BE (1) BE647227A (en)
DE (1) DE1209579B (en)
FR (1) FR1363360A (en)
GB (1) GB1005489A (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4056438A (en) * 1973-10-18 1977-11-01 Commissariat A L'energie Atomique Liquid sodium cooled fast reactor
US3994777A (en) * 1976-02-12 1976-11-30 The United States Of America As Represented By The United States Energy Research And Development Administration Nuclear reactor overflow line
US4294658A (en) * 1978-10-09 1981-10-13 United Kingdom Atomic Energy Authority Nuclear reactors

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE553108A (en) * 1955-12-02

Also Published As

Publication number Publication date
BE647227A (en) 1964-08-17
DE1209579B (en) 1966-01-27
GB1005489A (en) 1965-09-22

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