AR110991A1 - Aleaciones de circonio con resistencia a la corrosión y temperatura de servicio mejoradas para usar en el revestimiento del combustible y las partes estructurales del núcleo de un reactor nuclear - Google Patents

Aleaciones de circonio con resistencia a la corrosión y temperatura de servicio mejoradas para usar en el revestimiento del combustible y las partes estructurales del núcleo de un reactor nuclear

Info

Publication number
AR110991A1
AR110991A1 ARP180100400A ARP180100400A AR110991A1 AR 110991 A1 AR110991 A1 AR 110991A1 AR P180100400 A ARP180100400 A AR P180100400A AR P180100400 A ARP180100400 A AR P180100400A AR 110991 A1 AR110991 A1 AR 110991A1
Authority
AR
Argentina
Prior art keywords
fuel
coating
corrosion resistance
alloys
structural parts
Prior art date
Application number
ARP180100400A
Other languages
English (en)
Inventor
Gerardo Hctor Rubiolo
Liliana Alicia Lanzani
Laura Kniznik
Pablo Hugo Gargano
Mariano Daniel Forti
Pedro Antonio Ferreirs
Paula Regina Alonso
Original Assignee
Comision Nac De Energia Atomica Cnea
Univ Nacional De Gral San Martin Unsam
Univ Tecnologica Nacional Utn
Consejo Nacional De Investigaciones Cientificas Y Tecn Conicet
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 Comision Nac De Energia Atomica Cnea, Univ Nacional De Gral San Martin Unsam, Univ Tecnologica Nacional Utn, Consejo Nacional De Investigaciones Cientificas Y Tecn Conicet filed Critical Comision Nac De Energia Atomica Cnea
Priority to ARP180100400A priority Critical patent/AR110991A1/es
Priority to PCT/IB2019/051425 priority patent/WO2019162876A1/es
Publication of AR110991A1 publication Critical patent/AR110991A1/es

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
    • G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
    • 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
    • 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)
  • Metallurgy (AREA)
  • Physics & Mathematics (AREA)
  • Mechanical Engineering (AREA)
  • Organic Chemistry (AREA)
  • Materials Engineering (AREA)
  • Thermal Sciences (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Manufacture Of Metal Powder And Suspensions Thereof (AREA)
  • Physical Vapour Deposition (AREA)

Abstract

Se refiere a aleaciones de circonio (Zr) con pequeños porcentajes de niobio (Nb) y tantalio (Ta), con resistencia a la corrosión y temperatura de servicio, para la utilización en zonas de elevado flujo neutrónico de los reactores nucleares tales como el revestimiento del combustible y partes estructurales del núcleo.
ARP180100400A 2018-02-21 2018-02-21 Aleaciones de circonio con resistencia a la corrosión y temperatura de servicio mejoradas para usar en el revestimiento del combustible y las partes estructurales del núcleo de un reactor nuclear AR110991A1 (es)

Priority Applications (2)

Application Number Priority Date Filing Date Title
ARP180100400A AR110991A1 (es) 2018-02-21 2018-02-21 Aleaciones de circonio con resistencia a la corrosión y temperatura de servicio mejoradas para usar en el revestimiento del combustible y las partes estructurales del núcleo de un reactor nuclear
PCT/IB2019/051425 WO2019162876A1 (es) 2018-02-21 2019-02-21 Aleaciones de circonio con resistencia a la corrosión y temperatura de servicio mejoradas para usar en el revestimiento del combustible y las partes estructurales del núcleo de un reactor nuclear

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
ARP180100400A AR110991A1 (es) 2018-02-21 2018-02-21 Aleaciones de circonio con resistencia a la corrosión y temperatura de servicio mejoradas para usar en el revestimiento del combustible y las partes estructurales del núcleo de un reactor nuclear

Publications (1)

Publication Number Publication Date
AR110991A1 true AR110991A1 (es) 2019-05-22

Family

ID=66166263

Family Applications (1)

Application Number Title Priority Date Filing Date
ARP180100400A AR110991A1 (es) 2018-02-21 2018-02-21 Aleaciones de circonio con resistencia a la corrosión y temperatura de servicio mejoradas para usar en el revestimiento del combustible y las partes estructurales del núcleo de un reactor nuclear

Country Status (2)

Country Link
AR (1) AR110991A1 (es)
WO (1) WO2019162876A1 (es)

Family Cites Families (20)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS61146869A (ja) 1984-12-21 1986-07-04 平岡織染株式会社 繊維性基布の表面金属化方法
US4649023A (en) 1985-01-22 1987-03-10 Westinghouse Electric Corp. Process for fabricating a zirconium-niobium alloy and articles resulting therefrom
US5196163A (en) 1986-07-29 1993-03-23 Mitsubishi Materials Corporation Highly corrosion-resistant zirconium alloy for use as nuclear reactor fuel cladding material
FR2626291B1 (fr) 1988-01-22 1991-05-03 Mitsubishi Metal Corp Alliage a base de zirconium a utiliser comme assemblage pour combustible dans un reacteur nucleaire
US5230758A (en) 1989-08-28 1993-07-27 Westinghouse Electric Corp. Method of producing zirlo material for light water reactor applications
US5112573A (en) 1989-08-28 1992-05-12 Westinghouse Electric Corp. Zirlo material for light water reactor applications
JPH04224648A (ja) * 1990-12-25 1992-08-13 Kobe Steel Ltd 高耐蝕性・高強度ジルコニウム合金
FR2729000A1 (fr) 1994-12-29 1996-07-05 Framatome Sa Procede de fabrication d'un tube pour assemblage de combustible nucleaire et tubes conformes a ceux ainsi obtenus
US5838753A (en) 1997-08-01 1998-11-17 Siemens Power Corporation Method of manufacturing zirconium niobium tin alloys for nuclear fuel rods and structural parts for high burnup
JPH11194189A (ja) 1997-10-13 1999-07-21 Mitsubishi Materials Corp 耐食性およびクリープ特性にすぐれた原子炉燃料被覆管用Ｚｒ合金管の製造方法
KR100261666B1 (ko) 1998-02-04 2000-07-15 장인순 저 부식성과 고강도를 갖는 지르코늄합금 조성물
KR100261665B1 (ko) 1998-02-04 2000-07-15 장인순 우수한 부식저항성과 고강도를 갖는 지르코늄 합금조성물
US7985373B2 (en) 1998-03-31 2011-07-26 Framatome Anp Alloy and tube for nuclear fuel assembly and method for making same
RU2141539C1 (ru) 1999-04-22 1999-11-20 Государственный научный центр РФ Всероссийский научно-исследовательский институт неорганических материалов им.акад.А.А.Бочвара Сплав на основе циркония
KR100334252B1 (ko) 1999-11-22 2002-05-02 장인순 니오븀이 첨가된 핵연료피복관용 지르코늄 합금의 조성물
KR100733701B1 (ko) 2005-02-07 2007-06-28 한국원자력연구원 크립저항성이 우수한 지르코늄 합금 조성물
KR100831578B1 (ko) 2006-12-05 2008-05-21 한국원자력연구원 원자력용 우수한 내식성을 갖는 지르코늄 합금 조성물 및이의 제조방법
KR101557391B1 (ko) 2014-04-10 2015-10-07 한전원자력연료 주식회사 우수한 저수소흡수성 및 수소취화 저항성을 갖는 지르코늄합금의 제조방법 및 우수한 저수소흡수성 및 수소취화 저항성을 갖는 지르코늄합금 조성물
KR101604105B1 (ko) 2015-04-14 2016-03-16 한전원자력연료 주식회사 우수한 내식성 및 크리프 저항성을 갖는 지르코늄 합금과 그 제조방법
CN106929706A (zh) 2017-04-26 2017-07-07 上海核工程研究设计院 一种用于核反应堆高温环境中的锆基合金

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Publication number Publication date
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