AR094258A1 - 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
AR094258A1
AR094258A1 ARP130104998A ARP130104998A AR094258A1 AR 094258 A1 AR094258 A1 AR 094258A1 AR P130104998 A ARP130104998 A AR P130104998A AR P130104998 A ARP130104998 A AR P130104998A AR 094258 A1 AR094258 A1 AR 094258A1
Authority
AR
Argentina
Prior art keywords
temperature
treatment
materials
alloy
zone
Prior art date
Application number
ARP130104998A
Other languages
Spanish (es)
Inventor
Zhao Wenjin
Yang Zhongbo
Dai Xun
Miao Zhi
Yi Wei
Huang Zhaohua
Qiu Jun
Xu Chunrong
Wang Pengfei
Yan Meng
Dong Qionggen
zhuo Hong
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 AR094258A1 publication Critical patent/AR094258A1/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
    • 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
    • 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)
  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Metallurgy (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Organic Chemistry (AREA)
  • Thermal Sciences (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Preventing Corrosion Or Incrustation Of Metals (AREA)
  • Turbine Rotor Nozzle Sealing (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

Reivindicación 1: Un material de aleación de circonio para el núcleo de un reactor de energía nuclear, caracterizado por contener, en porcentaje por peso, los componentes siguientes: Sn: 0,60 - 1,00, Nb: 0,80 - 1,10, Fe: 0,10 - 0,40, Cu o Bi o Ge: 0 - 0,1, Si o S: 0 - 0,03, O: 0,06 - 0,15, C: menos de 0,008, N: menos de 0,006, el contenido residual es circonio. 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 para 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.Claim 1: A zirconium alloy material for the core of a nuclear power reactor, characterized by containing, in percentage by weight, the following components: Sn: 0.60-1.00, Nb: 0.80-1, 10, Fe: 0.10-0.40, Cu or Bi or Ge: 0-0.1, Si or S: 0-0.03, O: 0.06-0.15, C: less than 0.008, N: less than 0.006, the residual content is zirconium. 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 is performed to eliminate the tension and the annealing treatment of the recrystallization within the temperature of 460 ° C - 600 ° C to obtain the zirconium alloy materials.

ARP130104998A 2012-12-27 2013-12-20 CIRCONY ALLOY MATERIAL FOR THE NUCLEUS OF A NUCLEAR ENERGY REACTOR AND MATERIAL PREPARATION METHOD AR094258A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201210578429.XA CN103898363A (en) 2012-12-27 2012-12-27 Zirconium alloy for nuclear power

Publications (1)

Publication Number Publication Date
AR094258A1 true AR094258A1 (en) 2015-07-22

Family

ID=50989928

Family Applications (1)

Application Number Title Priority Date Filing Date
ARP130104998A AR094258A1 (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) CN103898363A (en)
AR (1) AR094258A1 (en)
GB (1) GB2523976B (en)
WO (1) WO2014101658A1 (en)
ZA (1) ZA201505321B (en)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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
CN105483444B (en) * 2015-12-09 2018-08-03 上海大学 Fuel for nuclear power plant involucrum zirconium niobium iron-based alloy
CN105568057B (en) * 2016-01-06 2020-04-28 中国核动力研究设计院 Zirconium alloy for nuclear reactor cladding material
CN112632771A (en) * 2020-12-21 2021-04-09 中国核动力研究设计院 Method and equipment for solving response sensitivity of fuel consumption calculation
CN113249616A (en) * 2021-04-08 2021-08-13 岭澳核电有限公司 Zirconium alloy for fuel assembly, preparation method thereof and cladding tube of fuel assembly
CN113326648B (en) * 2021-06-17 2022-02-22 中国核动力研究设计院 Cell homogenization constant calculation method and system considering environmental effect and terminal
CN115954122B (en) * 2022-12-30 2023-11-17 中国核动力研究设计院 Nuclear reactor pressure vessel fatigue state monitoring method, equipment and device

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6473038A (en) * 1987-09-14 1989-03-17 Toshiba Corp Corrosion-resistant zirconium alloy
FR2737335B1 (en) * 1995-07-27 1997-10-10 Framatome Sa TUBE FOR NUCLEAR FUEL ASSEMBLY AND METHOD FOR MANUFACTURING SUCH A TUBE
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
FR2874119B1 (en) * 2004-08-04 2006-11-03 Framatome Anp Sas METHOD FOR MANUFACTURING A FUEL SINK TUBE FOR A NUCLEAR REACTOR, AND A TUBE THUS OBTAINED
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.
CN101265538B (en) * 2008-03-24 2010-06-09 中国核动力研究设计院 Zirconium-base alloy used for light-water reactor
CN101413074A (en) * 2008-12-03 2009-04-22 西北有色金属研究院 Zirconium based alloy for nuclear reactor
CN101654752A (en) * 2009-09-22 2010-02-24 西北有色金属研究院 Zirconium-tin-niobium system zirconium alloy used by nuclear reactor
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
CN102660699B (en) * 2012-05-16 2014-02-12 上海大学 Zr-Sn-Nb-Fe-Si alloy for fuel cladding of nuclear power station

Also Published As

Publication number Publication date
CN103898363A (en) 2014-07-02
GB2523976B (en) 2018-10-17
ZA201505321B (en) 2016-10-26
GB201512802D0 (en) 2015-09-02
GB2523976A (en) 2015-09-09
WO2014101658A1 (en) 2014-07-03

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