FR1315685A - Perfectionnements aux réacteurs nucléaires - Google Patents

Perfectionnements aux réacteurs nucléaires

Info

Publication number
FR1315685A
FR1315685A FR888994A FR888994A FR1315685A FR 1315685 A FR1315685 A FR 1315685A FR 888994 A FR888994 A FR 888994A FR 888994 A FR888994 A FR 888994A FR 1315685 A FR1315685 A FR 1315685A
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
FR888994A
Other languages
English (en)
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.)
BELGE POUR L IND NUCLEAIRE BEL
Original Assignee
BELGE POUR L IND NUCLEAIRE BEL
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 BELGE POUR L IND NUCLEAIRE BEL filed Critical BELGE POUR L IND NUCLEAIRE BEL
Priority to FR888994A priority Critical patent/FR1315685A/fr
Application granted granted Critical
Publication of FR1315685A publication Critical patent/FR1315685A/fr
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10—Construction of control elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10—Construction of control elements
    • G21C7/11—Deformable control elements, e.g. flexible, telescopic, articulated
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/12—Means for moving control elements to desired position
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/12—Means for moving control elements to desired position
    • G21C7/16—Hydraulic or pneumatic drive
    • 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
FR888994A 1961-03-09 1962-02-23 Perfectionnements aux réacteurs nucléaires Expired FR1315685A (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR888994A FR1315685A (fr) 1961-03-09 1962-02-23 Perfectionnements aux réacteurs nucléaires

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
BE478347 1961-03-09
FR888994A FR1315685A (fr) 1961-03-09 1962-02-23 Perfectionnements aux réacteurs nucléaires

Publications (1)

Publication Number Publication Date
FR1315685A true FR1315685A (fr) 1963-01-18

Family

ID=25655292

Family Applications (1)

Application Number Title Priority Date Filing Date
FR888994A Expired FR1315685A (fr) 1961-03-09 1962-02-23 Perfectionnements aux réacteurs nucléaires

Country Status (1)

Country Link
FR (1) FR1315685A (fr)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1227576B (de) * 1963-12-02 1966-10-27 Atomic Energy Authority Uk Regelstabantrieb fuer Kernreaktoren
DE1240597B (de) * 1964-03-04 1967-05-18 Belge Pour L Ind Nucleaire Bel Hydraulische Einrichtung zur Betaetigung von Sicherheits- bzw. Regelstaeben in Kernreaktoren

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1227576B (de) * 1963-12-02 1966-10-27 Atomic Energy Authority Uk Regelstabantrieb fuer Kernreaktoren
DE1240597B (de) * 1964-03-04 1967-05-18 Belge Pour L Ind Nucleaire Bel Hydraulische Einrichtung zur Betaetigung von Sicherheits- bzw. Regelstaeben in Kernreaktoren

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