AR094256A1 - CIRCONY ALLOY MATERIAL FOR THE NUCLEUS OF A NUCLEAR ENERGY REACTOR AND MATERIAL PREPARATION METHOD - Google Patents

CIRCONY ALLOY MATERIAL FOR THE NUCLEUS OF A NUCLEAR ENERGY REACTOR AND MATERIAL PREPARATION METHOD

Info

Publication number
AR094256A1
AR094256A1 ARP130104996A ARP130104996A AR094256A1 AR 094256 A1 AR094256 A1 AR 094256A1 AR P130104996 A ARP130104996 A AR P130104996A AR P130104996 A ARP130104996 A AR P130104996A AR 094256 A1 AR094256 A1 AR 094256A1
Authority
AR
Argentina
Prior art keywords
alloy
materials
temperature
treatment
zirconium
Prior art date
Application number
ARP130104996A
Other languages
Spanish (es)
Inventor
Zhao Wenjin
Yang Zhongbo
Miao Zhi
Dai Xun
Yi Wei
Huang Zhaohua
Qiu Jun
Xu Chunrong
Liao Zhihai
Wang Pengfei
Dong Qionggen
Original Assignee
Nuclear Power Inst China
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 Nuclear Power Inst China filed Critical Nuclear Power Inst China
Publication of AR094256A1 publication Critical patent/AR094256A1/en

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C16/00—Alloys based on zirconium
    • 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
    • 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
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • 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
    • 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
    • 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)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Metallurgy (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Organic Chemistry (AREA)
  • Manufacturing & Machinery (AREA)
  • Thermal Sciences (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Powder Metallurgy (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

Pertenece al campo técnico de los materiales especiales de la aleación, especialmente se relaciona al un tipo de material de aleación del circonio usado para el núcleo del reactor de la energía nuclear. Se calcula su contenido del porcentaje por peso, que consiste en los componentes: Sn: 0,40 - 0,80, Nb: 0,75 - 1,10, Fe + Cr: 0,20 - 0,50, Fe / (Nb + Fe): 0,20 ~ 0,35, Cu o Bi o Ge: 0,01 - 0,1, Si o S: 0,002 - 0,02, O: 0,06 - 0,15, C: menos de 0,008, N: menos de 0,006; el contenido residual es circonio. Se agregan otros componentes para mejorar el rendimiento de aleación basado en la serie de Zr-Sn-Nb, se puede mejorar no sólo el rendimiento de resistencia a corrosión de la aleación, pero también las propiedades mecánicas y la resistencia a la radiación, por lo tanto, se cumple con los requisitos de los materiales de la estructura del núcleo del reactor para la alto consumo de combustión del reactor de la energía nuclear. Reivindicación 10: Un método de preparación del material de aleación de circonio según alguna de las reivindicaciones precedentes, caracterizado por los pasos siguientes: (1) se hace la dosificación según el coeficiente de la fórmula de todos los tipos de componentes de la aleación del circonio; (2) se implementa la fundición en el horno de arco del electrodo consumible del vacío para fabricar los lingotes de molde fundido de la aleación; (3) se fraguan los lingotes de molde fundido de la aleación a las materiales en las formas requeridas en la zona de la Fase b dentro la temperatura de 950ºC - 1080ºC; (4) se realiza la calefacción uniforme y el tratamiento de endurecimiento en la zona de la Fase b dentro la temperatura de 1000ºC - 1100ºC; (5) se realiza el tratamiento térmico de los materiales de lingote en la zona de la Fase a dentro la temperatura de 600ºC - 650ºC después del tratamiento de endurecimiento; (6) se realiza el tratamiento frío de los materiales de lingote después del tratamiento térmico, y se realiza el recocido intermedio dentro la temperatura de 550ºC - 620ºC; (7) se realiza el tratamiento de endurecimiento de eliminar la tensión y el tratamiento de recocido de la recristalización dentro la temperatura de 460ºC - 600ºC para obtener los materiales de la aleación del circonio.It belongs to the technical field of special alloy materials, especially it relates to a type of zirconium alloy material used for the nuclear power reactor core. Its content of the percentage by weight is calculated, which consists of the components: Sn: 0.40-0.80, Nb: 0.75-1.10, Fe + Cr: 0.20-0.50, Fe / ( Nb + Fe): 0.20 ~ 0.35, Cu or Bi or Ge: 0.01 - 0.1, Si or S: 0.002 - 0.02, O: 0.06 - 0.15, C: less 0.008, N: less than 0.006; The residual content is zirconium. Other components are added to improve the alloy performance based on the Zr-Sn-Nb series, not only the corrosion resistance performance of the alloy can be improved, but also the mechanical properties and radiation resistance, so Therefore, the requirements of the reactor core structure materials for the high combustion consumption of the nuclear power reactor are met. Claim 10: A method of preparing the zirconium alloy material according to any of the preceding claims, characterized by the following steps: (1) the dosage is made according to the formula coefficient of all types of zirconium alloy components ; (2) the melting in the arc furnace of the vacuum consumable electrode is implemented to manufacture the molten mold ingots of the alloy; (3) the cast mold ingots of the alloy are forged to the materials in the forms required in the zone of Phase b within the temperature of 950 ° C - 1080 ° C; (4) uniform heating and hardening treatment is carried out in the Phase b zone within the temperature of 1000 ° C - 1100 ° C; (5) the heat treatment of the ingot materials in the Phase zone is carried out at a temperature of 600 ° C - 650 ° C after the hardening treatment; (6) cold treatment of ingot materials is performed after heat treatment, and intermediate annealing is performed within the temperature of 550 ° C - 620 ° C; (7) The hardening treatment of removing the tension and the annealing treatment of the recrystallization is carried out at the temperature of 460 ° C - 600 ° C to obtain the zirconium alloy materials.

ARP130104996A 2012-12-27 2013-12-20 CIRCONY ALLOY MATERIAL FOR THE NUCLEUS OF A NUCLEAR ENERGY REACTOR AND MATERIAL PREPARATION METHOD AR094256A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201210578413.9A CN103898361B (en) 2012-12-27 2012-12-27 Zirconium alloy for nuclear reactor core

Publications (1)

Publication Number Publication Date
AR094256A1 true AR094256A1 (en) 2015-07-22

Family

ID=50989926

Family Applications (1)

Application Number Title Priority Date Filing Date
ARP130104996A AR094256A1 (en) 2012-12-27 2013-12-20 CIRCONY ALLOY MATERIAL FOR THE NUCLEUS OF A NUCLEAR ENERGY REACTOR AND MATERIAL PREPARATION METHOD

Country Status (5)

Country Link
CN (1) CN103898361B (en)
AR (1) AR094256A1 (en)
GB (1) GB2523975B (en)
WO (1) WO2014101660A1 (en)
ZA (1) ZA201505320B (en)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105483444B (en) * 2015-12-09 2018-08-03 上海大学 Fuel for nuclear power plant involucrum zirconium niobium iron-based alloy
CN105483443B (en) * 2015-12-09 2018-08-07 上海大学 The zirconium ferrocolumbium of fuel for nuclear power plant involucrum cupric and germanium
CN109692880B (en) * 2018-12-19 2021-01-01 西部超导材料科技股份有限公司 Zr-2.5Nb alloy bar and extrusion processing method thereof
CN113462998B (en) * 2020-03-30 2023-05-02 国核宝钛锆业股份公司 Preparation method of Zr-Nb alloy bar
CN117292852B (en) * 2023-11-27 2024-03-08 西安稀有金属材料研究院有限公司 Zirconium hydride moderating material and preparation method thereof

Family Cites Families (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2737335B1 (en) * 1995-07-27 1997-10-10 Framatome Sa TUBE FOR NUCLEAR FUEL ASSEMBLY AND METHOD FOR MANUFACTURING SUCH A TUBE
KR100382997B1 (en) * 2001-01-19 2003-05-09 한국전력공사 Method of Manufacturing A Tube and A Sheet of Niobium-containing Zirconium Alloys for High Burn-up Nuclear Fuel
KR100461017B1 (en) * 2001-11-02 2004-12-09 한국수력원자력 주식회사 Method for preparing niobium-containing zirconium alloys for nuclear fuel cladding tubes having the excellent corrosion resistance
FR2860803B1 (en) * 2003-10-08 2006-01-06 Cezus Co Europ Zirconium PROCESS FOR PRODUCING A ZIRCONIUM ALLOY FLAT PRODUCT, FLAT PRODUCT THUS OBTAINED, AND NUCLEAR POWER PLANT REACTOR GRADE REALIZED FROM THE FLAT PRODUCT
FR2909388B1 (en) * 2006-12-01 2009-01-16 Areva Np Sas CORROSION RESISTANT ZIRCONIUM ALLOY FOR FUEL ASSEMBLING COMPONENT FOR BOILING WATER REACTOR, COMPONENT PRODUCED THEREBY, FUEL ASSEMBLY AND USE THEREOF.
KR100999387B1 (en) * 2008-02-29 2010-12-09 한국원자력연구원 Zirconium alloy compositions having excellent corrosion resistance by the control of various metal-oxide and precipitate and preparation method thereof
CN101270425B (en) * 2008-03-24 2010-08-11 中国核动力研究设计院 Zirconium based alloy for light-water reactor
CN102212719B (en) * 2011-06-14 2013-01-16 苏州热工研究院有限公司 Low-tin-zirconium alloy material for nuclear reactor
CN102268571A (en) * 2011-06-30 2011-12-07 苏州热工研究院有限公司 Zirconium alloy material
CN102433465A (en) * 2011-12-14 2012-05-02 国核宝钛锆业股份公司 Bismuth-zirconium alloy
CN102605213B (en) * 2011-12-20 2014-06-11 上海大学 Germanium-containing Zr-Sn-Nb alloy for fuel cladding of nuclear power station

Also Published As

Publication number Publication date
CN103898361B (en) 2017-02-22
CN103898361A (en) 2014-07-02
GB2523975B (en) 2017-12-20
GB201512801D0 (en) 2015-09-02
WO2014101660A1 (en) 2014-07-03
GB2523975A (en) 2015-09-09
ZA201505320B (en) 2016-09-28

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