FR2036823A7 - Internal leakage protection for gas cooled - reactors - Google Patents

Internal leakage protection for gas cooled - reactors

Info

Publication number
FR2036823A7
FR2036823A7 FR6910491A FR6910491A FR2036823A7 FR 2036823 A7 FR2036823 A7 FR 2036823A7 FR 6910491 A FR6910491 A FR 6910491A FR 6910491 A FR6910491 A FR 6910491A FR 2036823 A7 FR2036823 A7 FR 2036823A7
Authority
FR
France
Prior art keywords
blocks
reactors
leakage protection
gas cooled
internal leakage
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
FR6910491A
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.)
Atomic Power Constructions Ltd
Original Assignee
Atomic Power Constructions 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 to DE19691916907 priority Critical patent/DE1916907A1/en
Application filed by Atomic Power Constructions Ltd filed Critical Atomic Power Constructions Ltd
Priority to FR6910491A priority patent/FR2036823A7/en
Application granted granted Critical
Publication of FR2036823A7 publication Critical patent/FR2036823A7/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • 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
    • G21C1/10—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 moderator and coolant being different or separated
    • G21C1/12—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 moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite 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

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)

Abstract

Artificial pressure differences are created along the graphic blocks of the reactor core which are sufficient to ensure the flow of coolant gas containing a corrosion inhibitor through the blocks. These differences are caused by shaping of the adjoining faces of the blocks forming the columns between the channels and are maintained by suitable joint seal, between blocks.
FR6910491A 1969-04-04 1969-04-04 Internal leakage protection for gas cooled - reactors Expired FR2036823A7 (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
DE19691916907 DE1916907A1 (en) 1969-04-04 1969-04-02 Nuclear Reactor Improvements
FR6910491A FR2036823A7 (en) 1969-04-04 1969-04-04 Internal leakage protection for gas cooled - reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR6910491A FR2036823A7 (en) 1969-04-04 1969-04-04 Internal leakage protection for gas cooled - reactors

Publications (1)

Publication Number Publication Date
FR2036823A7 true FR2036823A7 (en) 1970-12-31

Family

ID=9031958

Family Applications (1)

Application Number Title Priority Date Filing Date
FR6910491A Expired FR2036823A7 (en) 1969-04-04 1969-04-04 Internal leakage protection for gas cooled - reactors

Country Status (2)

Country Link
DE (1) DE1916907A1 (en)
FR (1) FR2036823A7 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115019985B (en) * 2022-03-22 2024-07-16 中核核电运行管理有限公司 Fuel channel leakage positioning device for heavy water reactor nuclear power unit

Also Published As

Publication number Publication date
DE1916907A1 (en) 1970-10-15

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Legal Events

Date Code Title Description
ST Notification of lapse