FR1335719A - Improvements to nuclear reactors - Google Patents

Improvements to nuclear reactors

Info

Publication number
FR1335719A
FR1335719A FR906911A FR906911A FR1335719A FR 1335719 A FR1335719 A FR 1335719A FR 906911 A FR906911 A FR 906911A FR 906911 A FR906911 A FR 906911A FR 1335719 A FR1335719 A FR 1335719A
Authority
FR
France
Prior art keywords
nuclear reactors
reactors
nuclear
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
FR906911A
Other languages
French (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 International Ltd
Original Assignee
Babcock and Wilcox Ltd
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
Priority claimed from GB29416/61A external-priority patent/GB1029836A/en
Application filed by Babcock and Wilcox Ltd filed Critical Babcock and Wilcox Ltd
Priority to FR906911A priority Critical patent/FR1335719A/en
Application granted granted Critical
Publication of FR1335719A publication Critical patent/FR1335719A/en
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
    • 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
FR906911A 1961-08-15 1962-08-14 Improvements to nuclear reactors Expired FR1335719A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR906911A FR1335719A (en) 1961-08-15 1962-08-14 Improvements to nuclear reactors

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB29416/61A GB1029836A (en) 1961-08-15 1961-08-15 Improvements in or relating to nuclear reactors
FR906911A FR1335719A (en) 1961-08-15 1962-08-14 Improvements to nuclear reactors

Publications (1)

Publication Number Publication Date
FR1335719A true FR1335719A (en) 1963-08-23

Family

ID=26197084

Family Applications (1)

Application Number Title Priority Date Filing Date
FR906911A Expired FR1335719A (en) 1961-08-15 1962-08-14 Improvements to nuclear reactors

Country Status (1)

Country Link
FR (1) FR1335719A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1911637C3 (en) * 1968-03-08 1973-07-05 Snam Progetti Mechanical sealing arrangement for sodium circulating as coolant inside a nuclear reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1911637C3 (en) * 1968-03-08 1973-07-05 Snam Progetti Mechanical sealing arrangement for sodium circulating as coolant inside a nuclear reactor

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