IT8321303A1 - Controllo di differenza di crescita in componenti di reattori nucleari mediante controllo di condizioni metallurgiche - Google Patents

Controllo di differenza di crescita in componenti di reattori nucleari mediante controllo di condizioni metallurgiche

Info

Publication number
IT8321303A1
IT8321303A1 IT1983A21303A IT2130383A IT8321303A1 IT 8321303 A1 IT8321303 A1 IT 8321303A1 IT 1983A21303 A IT1983A21303 A IT 1983A21303A IT 2130383 A IT2130383 A IT 2130383A IT 8321303 A1 IT8321303 A1 IT 8321303A1
Authority
IT
Italy
Prior art keywords
control
metallurgic
nuclear reactor
reactor components
growth difference
Prior art date
Application number
IT1983A21303A
Other languages
English (en)
Other versions
IT1171072B (it
IT8321303A0 (it
Original Assignee
Gen Electric
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 Gen Electric filed Critical Gen Electric
Publication of IT8321303A0 publication Critical patent/IT8321303A0/it
Publication of IT8321303A1 publication Critical patent/IT8321303A1/it
Application granted granted Critical
Publication of IT1171072B publication Critical patent/IT1171072B/it

Links

Classifications

    • 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
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22F—CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
    • C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
    • C22F1/16—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of other metals or alloys based thereon
    • C22F1/18—High-melting or refractory metals or alloys based thereon
    • C22F1/186—High-melting or refractory metals or alloys based thereon of zirconium or alloys based thereon
    • 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
    • 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
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00—Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90—Particular material or material shapes for fission reactors
    • Y10S376/904—Moderator, reflector, or coolant materials
    • Y10S376/906—Metal

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Thermal Sciences (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Heat Treatment Of Nonferrous Metals Or Alloys (AREA)
  • Metal Extraction Processes (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
IT21303/83A 1982-06-01 1983-05-26 Controllo di differenza di crescita in componenti di reattori nucleari mediante controllo di condizioni metallurgiche IT1171072B (it)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US06/383,808 US4770847A (en) 1982-06-01 1982-06-01 Control of differential growth in nuclear reactor components by control of metallurgical conditions

Publications (3)

Publication Number Publication Date
IT8321303A0 IT8321303A0 (it) 1983-05-26
IT8321303A1 true IT8321303A1 (it) 1984-11-26
IT1171072B IT1171072B (it) 1987-06-10

Family

ID=23514806

Family Applications (1)

Application Number Title Priority Date Filing Date
IT21303/83A IT1171072B (it) 1982-06-01 1983-05-26 Controllo di differenza di crescita in componenti di reattori nucleari mediante controllo di condizioni metallurgiche

Country Status (5)

Country Link
US (1) US4770847A (it)
JP (1) JPS5916955A (it)
DE (1) DE3318584A1 (it)
ES (1) ES522690A0 (it)
IT (1) IT1171072B (it)

Families Citing this family (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4678632A (en) * 1985-06-05 1987-07-07 Westinghouse Electric Corp. Nuclear fuel assembly grid with predetermined grain orientation
SE464267B (sv) * 1985-10-22 1991-03-25 Westinghouse Electric Corp Roerformig kaernbraenslekapsel
US4990305A (en) * 1989-06-28 1991-02-05 Westinghouse Electric Corp. Single peak radial texture zircaloy tubing
US5350161A (en) * 1991-02-26 1994-09-27 Combustion Engineering, Inc. Nuclear reactor grid strip cantilever spring with nonuniform material characteristics
SE506174C2 (sv) * 1992-12-18 1997-11-17 Asea Atom Ab Metod att framställa kärnbränsleelement
SE502866C2 (sv) * 1993-06-30 1996-02-05 Asea Atom Ab Bränsleelement för tryckvattenreaktor vars ledrör är slutvärmebehandlade i två steg
US6167104A (en) * 1996-09-04 2000-12-26 Siemens Aktiengesellschaft Pressurized water reactor fuel assembly with a guide tube and method for producing the guide tube
SE525455C2 (sv) * 2002-06-07 2005-02-22 Westinghouse Atom Ab Förfarande, användning och anordning beträffande kapslingsrör för kärnbränsle samt bränslepatron för en nukleär kokarvattenreaktor

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2894866A (en) * 1958-01-21 1959-07-14 Marion L Picklesimer Method for annealing and rolling zirconium-base alloys
GB1097571A (en) * 1965-03-01 1968-01-03 Atomic Energy Authority Uk Improvements in or relating to tubes
US3567522A (en) * 1965-12-15 1971-03-02 Westinghouse Electric Corp Method of producing zirconium base alloys
BE789401A (fr) * 1971-09-30 1973-01-15 Gen Electric Assemblage de barres de combustible pour reacteurs nucleaires
CA1025335A (en) * 1972-09-05 1978-01-31 Ake S.B. Hofvenstam Method of making tubes and similar products of a zirconium alloy
US4238251A (en) * 1977-11-18 1980-12-09 General Electric Company Zirconium alloy heat treatment process and product
US4239597A (en) * 1978-03-30 1980-12-16 The Babcock & Wilcox Company Nuclear fuel spacer grid
CA1139023A (en) * 1979-06-04 1983-01-04 John H. Davies Thermal-mechanical treatment of composite nuclear fuel element cladding

Also Published As

Publication number Publication date
IT1171072B (it) 1987-06-10
DE3318584A1 (de) 1983-12-01
DE3318584C2 (it) 1987-04-23
IT8321303A0 (it) 1983-05-26
US4770847A (en) 1988-09-13
ES8502568A1 (es) 1985-01-01
JPS5916955A (ja) 1984-01-28
JPS6155584B2 (it) 1986-11-28
ES522690A0 (es) 1985-01-01

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Legal Events

Date Code Title Description
TA Fee payment date (situation as of event date), data collected since 19931001

Effective date: 19930511