FR2073382B1 - - Google Patents

Info

Publication number
FR2073382B1
FR2073382B1 FR7041307A FR7041307A FR2073382B1 FR 2073382 B1 FR2073382 B1 FR 2073382B1 FR 7041307 A FR7041307 A FR 7041307A FR 7041307 A FR7041307 A FR 7041307A FR 2073382 B1 FR2073382 B1 FR 2073382B1
Authority
FR
France
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
FR7041307A
Other versions
FR2073382A1 (fr
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.)
Babcock and Wilcox Co
Original Assignee
Babcock and Wilcox Co
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 Babcock and Wilcox Co filed Critical Babcock and Wilcox Co
Publication of FR2073382A1 publication Critical patent/FR2073382A1/fr
Application granted granted Critical
Publication of FR2073382B1 publication Critical patent/FR2073382B1/fr
Expired legal-status Critical Current

Links

Classifications

    • 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
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • 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
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • 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
    • 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
    • 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
FR7041307A 1969-11-19 1970-11-18 Expired FR2073382B1 (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US87812569A 1969-11-19 1969-11-19

Publications (2)

Publication Number Publication Date
FR2073382A1 FR2073382A1 (fr) 1971-10-01
FR2073382B1 true FR2073382B1 (fr) 1975-02-21

Family

ID=25371438

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7041307A Expired FR2073382B1 (fr) 1969-11-19 1970-11-18

Country Status (4)

Country Link
US (1) US3700552A (fr)
CA (1) CA932484A (fr)
FR (1) FR2073382B1 (fr)
GB (1) GB1335380A (fr)

Families Citing this family (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2345081C3 (de) * 1973-09-06 1980-05-29 Kraftwerk Union Ag, 4330 Muelheim Hauptkühlmittelpumpe für Kernreaktoren
US4000037A (en) * 1973-11-28 1976-12-28 Westinghouse Electric Corporation Reactor-turbine control for low steam pressure operation in a pressurized water reactor
US4187147A (en) * 1976-02-20 1980-02-05 Westinghouse Electric Corp. Recirculation system for nuclear reactors
US4222822A (en) * 1977-01-19 1980-09-16 Westinghouse Electric Corp. Method for operating a nuclear reactor to accommodate load follow while maintaining a substantially constant axial power distribution
US4187144A (en) * 1977-05-23 1980-02-05 Westinghouse Electric Corp. Nuclear reactor power supply
DE2942013C2 (de) * 1978-10-18 1984-10-18 Hitachi, Ltd., Tokio/Tokyo Verfahren und Anordnung zur Regelung eines Siedewasserreaktors
US4412969A (en) * 1982-03-09 1983-11-01 Tilbrook Roger W Combination pipe rupture mitigator and in-vessel core catcher
US4500583A (en) * 1983-09-12 1985-02-19 Owens-Corning Fiberglas Corporation Honeycomb structure
JPS6069598A (ja) * 1983-09-21 1985-04-20 株式会社日立製作所 原子炉起動法
DE102012007411A1 (de) * 2012-04-16 2013-10-17 Areva Gmbh Speisewasserverteilsystem für ein Kernkraftwerk und Verfahren zum Betreiben eines Kernkraftwerks
WO2021128060A1 (fr) * 2019-12-25 2021-07-01 中广核研究院有限公司 Système d'essai tridimensionnel et dispositif d'essai tridimensionnel pour simuler des caractéristiques de transfert de chaleur d'une cuve sous pression de réacteur d'une centrale nucléaire

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1272893A (fr) * 1960-11-07 1961-09-29 Licentia Gmbh Procédé d'accroissement du rendement calorifique d'un réacteur nucléaire

Also Published As

Publication number Publication date
CA932484A (en) 1973-08-21
FR2073382A1 (fr) 1971-10-01
GB1335380A (en) 1973-10-24
US3700552A (en) 1972-10-24

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Legal Events

Date Code Title Description
ST Notification of lapse