GB1486064A - Method of heat-treating cladding materials for nuclear reactor fuel elements - Google Patents

Method of heat-treating cladding materials for nuclear reactor fuel elements

Info

Publication number
GB1486064A
GB1486064A GB8707/75A GB870775A GB1486064A GB 1486064 A GB1486064 A GB 1486064A GB 8707/75 A GB8707/75 A GB 8707/75A GB 870775 A GB870775 A GB 870775A GB 1486064 A GB1486064 A GB 1486064A
Authority
GB
United Kingdom
Prior art keywords
heat
nuclear reactor
fuel elements
reactor fuel
treated
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
GB8707/75A
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.)
Gesellschaft fuer Kernforschung mbH
Original Assignee
Gesellschaft fuer Kernforschung mbH
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 Gesellschaft fuer Kernforschung mbH filed Critical Gesellschaft fuer Kernforschung mbH
Publication of GB1486064A publication Critical patent/GB1486064A/en
Expired legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C21—METALLURGY OF IRON
    • C21D—MODIFYING THE PHYSICAL STRUCTURE OF FERROUS METALS; GENERAL DEVICES FOR HEAT TREATMENT OF FERROUS OR NON-FERROUS METALS OR ALLOYS; MAKING METAL MALLEABLE, e.g. BY DECARBURISATION OR TEMPERING
    • C21D8/00—Modifying the physical properties by deformation combined with, or followed by, heat treatment
    • C21D8/005—Modifying the physical properties by deformation combined with, or followed by, heat treatment of ferrous alloys
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (AREA)
  • Metallurgy (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • Materials Engineering (AREA)
  • Organic Chemistry (AREA)
  • Manufacturing & Machinery (AREA)
  • Mechanical Engineering (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Thermal Sciences (AREA)
  • Heat Treatment Of Steel (AREA)

Abstract

1486064 Heat-treating stainless steel GES FUER KERNFORSCHUNG mbH 3 March 1975 [2 April 1974] 8707/75 Heading C7A A stainless steel for cladding nuclear reactor fuel elements is solution treated, precipitation treated at 750-900‹C to form both grain boundary and intra granular precipitates and then cold worked (up to 200‹C) to produce 7 to 20% deformation. Preferred conditions are a solution treatment temperature above 1000‹C, precipitation at 750-850‹C and 15% reduction, while as exemplified at 15% Ni, 15% Cr, Ti, B steel is treated at 1150‹C and then at 800‹C.
GB8707/75A 1974-04-02 1975-03-03 Method of heat-treating cladding materials for nuclear reactor fuel elements Expired GB1486064A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2415881A DE2415881A1 (en) 1974-04-02 1974-04-02 PROCESS FOR PRODUCING METALLIC SHELLING MATERIALS FOR FAST REACTORS

Publications (1)

Publication Number Publication Date
GB1486064A true GB1486064A (en) 1977-09-14

Family

ID=5911916

Family Applications (1)

Application Number Title Priority Date Filing Date
GB8707/75A Expired GB1486064A (en) 1974-04-02 1975-03-03 Method of heat-treating cladding materials for nuclear reactor fuel elements

Country Status (4)

Country Link
DE (1) DE2415881A1 (en)
FR (1) FR2266263B1 (en)
GB (1) GB1486064A (en)
SE (1) SE7503521L (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0090115A2 (en) * 1982-03-31 1983-10-05 Westinghouse Electric Corporation Cold worked ferritic alloys and components
US5949838A (en) * 1992-12-18 1999-09-07 Electric Power Research Institute, Inc. Manufacture of materials and workpieces for components in nuclear plant applications
US6132525A (en) * 1992-12-18 2000-10-17 Electric Power Research Institute, Inc. Manufacturing of materials and workpieces for components in nuclear plant applications

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2058834B (en) * 1979-07-27 1984-07-25 Westinghouse Electric Corp Method for heat treating iron-nickel-chromium alloys
US4359350A (en) * 1981-03-27 1982-11-16 The United States Of America As Represented By The Department Of Energy High post-irradiation ductility thermomechanical treatment for precipitation strengthened austenitic alloys
EP0593470A1 (en) * 1991-07-10 1994-04-27 Siemens Aktiengesellschaft Material and workpiece for nuclear engineering and production thereof

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0090115A2 (en) * 1982-03-31 1983-10-05 Westinghouse Electric Corporation Cold worked ferritic alloys and components
EP0090115A3 (en) * 1982-03-31 1985-04-03 Westinghouse Electric Corporation Cold worked ferritic alloys and components
US5949838A (en) * 1992-12-18 1999-09-07 Electric Power Research Institute, Inc. Manufacture of materials and workpieces for components in nuclear plant applications
US6132525A (en) * 1992-12-18 2000-10-17 Electric Power Research Institute, Inc. Manufacturing of materials and workpieces for components in nuclear plant applications

Also Published As

Publication number Publication date
FR2266263A1 (en) 1975-10-24
DE2415881A1 (en) 1975-10-23
FR2266263B1 (en) 1979-04-06
SE7503521L (en) 1975-10-03

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee