ES8502568A1 - Procedimiento para obtener diferentes grados de crecimiento por irradiacion entre un primer tubo de envainado hecho de un metal anisotropico y un segundo tubo de envainado hecho del mismo metal anisotropico. - Google Patents

Procedimiento para obtener diferentes grados de crecimiento por irradiacion entre un primer tubo de envainado hecho de un metal anisotropico y un segundo tubo de envainado hecho del mismo metal anisotropico.

Info

Publication number
ES8502568A1
ES8502568A1 ES522690A ES522690A ES8502568A1 ES 8502568 A1 ES8502568 A1 ES 8502568A1 ES 522690 A ES522690 A ES 522690A ES 522690 A ES522690 A ES 522690A ES 8502568 A1 ES8502568 A1 ES 8502568A1
Authority
ES
Spain
Prior art keywords
control
nuclear reactor
reactor components
energy state
differential growth
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
ES522690A
Other languages
English (en)
Other versions
ES522690A0 (es
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.)
General Electric Co
Original Assignee
General Electric Co
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 General Electric Co filed Critical General Electric Co
Publication of ES522690A0 publication Critical patent/ES522690A0/es
Publication of ES8502568A1 publication Critical patent/ES8502568A1/es
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22FCHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
    • C22F1/00Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
    • C22F1/16Changing 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
    • C22F1/18High-melting or refractory metals or alloys based thereon
    • C22F1/186High-melting or refractory metals or alloys based thereon of zirconium or alloys based thereon
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C21/00Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • YGENERAL 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
    • Y10TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10STECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90Particular material or material shapes for fission reactors
    • Y10S376/904Moderator, reflector, or coolant materials
    • Y10S376/906Metal

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)

Abstract

PROCEDIMIENTO PARA OBTENER DIFERENTES GRADOS DE CRECIMIENTO POR IRRADIACION ENTRE UN PRIMER TUBO DE ENVAINADO HECHO DE UN METAL ANISOTROPICO Y UN SEGUNDO TUBO DE ENVAINADO HECHO DEL MISMO METAL ANISOTROPICO.CONSISTE EN FORMAR UN PRIMER TUBO DE ENVAINADO SIGUIENDO UN PRIMER PROGRAMA DE FABRICACION, EN EL QUE SE TRATA TERMICAMENTE A DICHO TUBO A UNA TEMPERATURA SUFICIENTE PARA INDUCIR UNA RECRISTALIZACION COMPLETA SIN INDUCIR UN CRECIMIENTO SUSTANCIAL DE LOS GRANOS, Y EN FORMAR UN SEGUNDO TUBO DE ENVAINADO SIGUIENDO UN SEGUNDO PROGRAMA DE FABRICACION, EN EL QUE DICHO TUBO SE TRATA TERMICAMENTE, PARA PRODUCIR UNA RECRISTALIZACION PARCIAL.
ES522690A 1982-06-01 1983-05-25 Procedimiento para obtener diferentes grados de crecimiento por irradiacion entre un primer tubo de envainado hecho de un metal anisotropico y un segundo tubo de envainado hecho del mismo metal anisotropico. Expired ES8502568A1 (es)

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 (2)

Publication Number Publication Date
ES522690A0 ES522690A0 (es) 1985-01-01
ES8502568A1 true ES8502568A1 (es) 1985-01-01

Family

ID=23514806

Family Applications (1)

Application Number Title Priority Date Filing Date
ES522690A Expired ES8502568A1 (es) 1982-06-01 1983-05-25 Procedimiento para obtener diferentes grados de crecimiento por irradiacion entre un primer tubo de envainado hecho de un metal anisotropico y un segundo tubo de envainado hecho del mismo metal anisotropico.

Country Status (5)

Country Link
US (1) US4770847A (es)
JP (1) JPS5916955A (es)
DE (1) DE3318584A1 (es)
ES (1) ES8502568A1 (es)
IT (1) IT1171072B (es)

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
US3865635A (en) * 1972-09-05 1975-02-11 Sandvik Ab 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
US4770847A (en) 1988-09-13
DE3318584C2 (es) 1987-04-23
ES522690A0 (es) 1985-01-01
IT1171072B (it) 1987-06-10
IT8321303A0 (it) 1983-05-26
IT8321303A1 (it) 1984-11-26
JPS5916955A (ja) 1984-01-28
JPS6155584B2 (es) 1986-11-28
DE3318584A1 (de) 1983-12-01

Similar Documents

Publication Publication Date Title
DE3312803C2 (es)
JP3082369B2 (ja) 燃料チャンネルボックスの製造法及び燃料集合体の製造法並びに使用方法
ES8502568A1 (es) Procedimiento para obtener diferentes grados de crecimiento por irradiacion entre un primer tubo de envainado hecho de un metal anisotropico y un segundo tubo de envainado hecho del mismo metal anisotropico.
SE8500900L (sv) Metod for drift av kernkraftverk av typen med kokande vatten
TW357369B (en) Method of manufacturing zirconium tin iron alloys for nuclear fuel rods and structural parts for high burnup
ES8608719A1 (es) Perfeccionamientos en los sistemas de vigilancia de las condiciones operativas de un reactor
GB840740A (en) A steam stirred homogeneous nuclear reactor
ES8402968A1 (es) Procedimiento para la obtencion de cuerpos sinterizados de combustible nuclear oxidico.
GB1060999A (en) Liquid metal fast breeder reactor
ES8703945A1 (es) Procedimiento para mejorar la resistencia a la corrosion producida por vapor de agua a temperatura elevada de un cuerpo de aleacion de zirconio alfa.
FR2356243A1 (fr) Structure de combustible nucleaire utile comme cible pour la production de molybdene-99
GB1057529A (en) Method of controlling a nuclear reactor
GB1486064A (en) Method of heat-treating cladding materials for nuclear reactor fuel elements
GB1251939A (es)
GB979747A (en) Improvements in the cladding of metal
McDonell et al. High-performance uranium-metal fuels for Savannah River reactors
US3219541A (en) Method of preventing carburization of fuel element cladding metals by uranium carbide fuels
US3743575A (en) Method of heating a sample material to a high temperature by using a relatively low power nuclear reactor
JP3492881B2 (ja) 燃料チャンネルボックス及び燃料集合体
JP3191813B2 (ja) 燃料チャンネルボックス及び燃料集合体並びに使用方法
Demin et al. Studying the problems of calculational homogenization of absorbing rods placed in a radial reflector
Sowden et al. FISSION RECOIL DECOMPOSITION OF CALCIUM NITRATE SOLUTIONS
GB1335509A (en) Method for the treatment of irradiated nuclear fuel elements
GB843307A (en) Plutonium-uranium-titanium alloys
EP0065816A3 (en) Zirconium based alloy