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
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)
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.
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)
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)
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 |
-
1982
- 1982-06-01 US US06/383,808 patent/US4770847A/en not_active Expired - Lifetime
-
1983
- 1983-05-21 DE DE19833318584 patent/DE3318584A1/de active Granted
- 1983-05-25 ES ES522690A patent/ES8502568A1/es not_active Expired
- 1983-05-26 IT IT21303/83A patent/IT1171072B/it active
- 1983-06-01 JP JP58095896A patent/JPS5916955A/ja active Granted
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 |