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RU2002124765A - ALLOY OF ZIRCONIUM-NIOBIUM-TIN FOR USE IN ATOMIC REACTORS AND METHOD FOR PRODUCING IT - Google Patents

ALLOY OF ZIRCONIUM-NIOBIUM-TIN FOR USE IN ATOMIC REACTORS AND METHOD FOR PRODUCING IT

Info

Publication number
RU2002124765A
RU2002124765A RU2002124765/02A RU2002124765A RU2002124765A RU 2002124765 A RU2002124765 A RU 2002124765A RU 2002124765/02 A RU2002124765/02 A RU 2002124765/02A RU 2002124765 A RU2002124765 A RU 2002124765A RU 2002124765 A RU2002124765 A RU 2002124765A
Authority
RU
Russia
Prior art keywords
content
alloy
alloy according
tin
zirconium
Prior art date
Application number
RU2002124765/02A
Other languages
Russian (ru)
Inventor
Роберт Дж. КОМСТОК (US)
Роберт Дж. КОМСТОК
Джордж П. СЭБОЛ (US)
Джордж П. СЭБОЛ
Original Assignee
Вестингхаус Электрик Компани Ллс (Us)
Вестингхаус Электрик Компани Ллс
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 Вестингхаус Электрик Компани Ллс (Us), Вестингхаус Электрик Компани Ллс filed Critical Вестингхаус Электрик Компани Ллс (Us)
Publication of RU2002124765A publication Critical patent/RU2002124765A/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
    • 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
    • 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
    • G21C3/16—Details of the construction within the casing
    • G21C3/20—Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
    • 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)
  • Organic Chemistry (AREA)
  • Mechanical Engineering (AREA)
  • Materials Engineering (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Thermal Sciences (AREA)
  • Powder Metallurgy (AREA)
  • Preventing Corrosion Or Incrustation Of Metals (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Claims (8)

1. Циркониевый сплав с низким содержанием олова, состоящий в массовых процентах по существу из 0,60-2,0 Nb при таком соотношении между содержаниями Sn и Fe, которое определяется областью, заключенной на графике олово vs железо внутри фигуры со следующими координатами: когда Sn составляет 0,25, тогда Fe составляет 0,50; когда Sn составляет 0,40, тогда Fe составляет от 0,35 до 0,50; когда Sn составляет 0,50, тогда Fe составляет от 0,25 до 0,50; когда Sn составляет 0,65, тогда Fe составляет от 0,10 до 0,50; когда Sn составляет 0,70, тогда Fe составляет от 0,05 до 0,50; когда Sn составляет 0,85, тогда Fe составляет от 0,05 до 0,50; и где массовое процентное содержание Fe плюс Sn больше, чем 0,75, при этом другие дополнительные компоненты сплава составляют не более 0,50, а остальное количество составляет Zr.1. Zirconium alloy with a low tin content, consisting in mass percent of essentially 0.60-2.0 Nb at a ratio between the contents of Sn and Fe, which is determined by the region enclosed in the tin vs iron graph inside the figure with the following coordinates: when Sn is 0.25, then Fe is 0.50; when Sn is 0.40, then Fe is from 0.35 to 0.50; when Sn is 0.50, then Fe is from 0.25 to 0.50; when Sn is 0.65, then Fe is from 0.10 to 0.50; when Sn is 0.70, then Fe is 0.05 to 0.50; when Sn is 0.85, then Fe is from 0.05 to 0.50; and where the mass percentage of Fe plus Sn is greater than 0.75, while other additional alloy components are not more than 0.50, and the remaining amount is Zr. 2. Сплав по п.1, отличающийся тем, что содержание Sn в массовых процентах составляет от 0,25 до 0,85, где верхний предел 0,85 обеспечивает хорошую высокотемпературную коррозионную стойкость, а нижний предел, зависящий от содержания железа, обеспечивает стойкость к коррозии в литиированной воде.2. The alloy according to claim 1, characterized in that the content of Sn in mass percent is from 0.25 to 0.85, where the upper limit of 0.85 provides good high-temperature corrosion resistance, and the lower limit, depending on the iron content, provides resistance to corrosion in lithiated water. 3. Сплав по п.1 или 2, отличающийся тем, что содержание Fe в массовых процентах составляет от 0,05 до 0,5, где содержание Fe зависит от содержания Sn.3. The alloy according to claim 1 or 2, characterized in that the Fe content in mass percent is from 0.05 to 0.5, where the Fe content depends on the content of Sn. 4. Сплав по любому из пп.1-3, отличающийся тем, что содержит не более, чем 0,30 других дополнительных элементов, являющихся компонентами сплава.4. The alloy according to any one of claims 1 to 3, characterized in that it contains no more than 0.30 other additional elements that are components of the alloy. 5. Сплав по любому из пп.1-4, отличающийся тем, что является стойким к коррозии в чистой воде и паре и в литиированной воде.5. The alloy according to any one of claims 1 to 4, characterized in that it is resistant to corrosion in pure water and steam and in lithiated water. 6. Материал элементов атомного реактора, полученный из сплава по любому из пп.1-5.6. The material of the elements of an atomic reactor obtained from an alloy according to any one of claims 1 to 5. 7. Циркониевый сплав с низким содержанием олова по любому из пп.1-5, отличающийся тем, что содержание Sn составляет от 0,65 мас.% до 0,85 мас.%.7. Zirconium alloy with a low tin content according to any one of claims 1 to 5, characterized in that the Sn content is from 0.65 wt.% To 0.85 wt.%. 8. Способ получения сплава по любому из пп.1-5, 7, включающий в себя следующие стадии, на которых:8. The method of producing an alloy according to any one of claims 1 to 5, 7, comprising the following stages, in which: (1) смешивают сухие ингредиенты;(1) dry ingredients are mixed; (2) расплавляют ингредиенты в вакууме;(2) melt the ingredients in a vacuum; (3) проводят ковку расплава с получением желаемой формы;(3) forging the melt to obtain the desired shape; (4) проводят бета-теплообработку и резкое охлаждение;(4) conduct beta heat treatment and quenching; (5) проводят горячую обработку;(5) conduct hot processing; (6) проводят холодную обработку с промежуточными рекристаллизационными отжигами в альфа-фазовом температурном диапазоне;(6) carry out cold processing with intermediate recrystallization annealing in the alpha phase temperature range; (7) проводят конечный отжиг в форме снимающего напряжения отжига или рекристаллизационного отжига в температурном диапазоне 450-625°С.(7) conduct final annealing in the form of relieving annealing stress or recrystallization annealing in the temperature range 450-625 ° C.
RU2002124765/02A 2000-02-18 2001-01-19 ALLOY OF ZIRCONIUM-NIOBIUM-TIN FOR USE IN ATOMIC REACTORS AND METHOD FOR PRODUCING IT RU2002124765A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US50691300A 2000-02-18 2000-02-18
US09/506,913 2000-02-18

Publications (1)

Publication Number Publication Date
RU2002124765A true RU2002124765A (en) 2004-03-20

Family

ID=24016448

Family Applications (1)

Application Number Title Priority Date Filing Date
RU2002124765/02A RU2002124765A (en) 2000-02-18 2001-01-19 ALLOY OF ZIRCONIUM-NIOBIUM-TIN FOR USE IN ATOMIC REACTORS AND METHOD FOR PRODUCING IT

Country Status (7)

Country Link
EP (1) EP1259653A1 (en)
JP (1) JP2001262260A (en)
CN (1) CN1152146C (en)
AU (1) AU2001234492A1 (en)
RU (1) RU2002124765A (en)
SE (1) SE526648C2 (en)
WO (1) WO2001061062A1 (en)

Families Citing this family (17)

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Publication number Priority date Publication date Assignee Title
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
SE525808C2 (en) * 2002-10-30 2005-05-03 Westinghouse Atom Ab Process, use and device for nuclear fuel casing and a fuel cartridge for a nuclear pressurized water reactor
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
US9284629B2 (en) 2004-03-23 2016-03-15 Westinghouse Electric Company Llc Zirconium alloys with improved corrosion/creep resistance due to final heat treatments
US10221475B2 (en) 2004-03-23 2019-03-05 Westinghouse Electric Company Llc Zirconium alloys with improved corrosion/creep resistance
WO2006004499A1 (en) * 2004-07-06 2006-01-12 Westinghouse Electric Sweden Ab Fuel box in a boiling water nuclear reactor
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
JP4982654B2 (en) * 2005-03-23 2012-07-25 ウエスチングハウス・エレクトリック・カンパニー・エルエルシー Zirconium alloy with improved corrosion resistance and method for producing zirconium alloy with improved corrosion resistance
US7625453B2 (en) 2005-09-07 2009-12-01 Ati Properties, Inc. Zirconium strip material and process for making same
US8116422B2 (en) * 2005-12-29 2012-02-14 General Electric Company LWR flow channel with reduced susceptibility to deformation and control blade interference under exposure to neutron radiation and corrosion fields
SE530673C2 (en) 2006-08-24 2008-08-05 Westinghouse Electric Sweden Water reactor fuel cladding tube used in pressurized water reactor and boiled water reactor, comprises outer layer of zirconium based alloy which is metallurgically bonded to inner layer of another zirconium based alloy
KR100835830B1 (en) 2007-01-11 2008-06-05 한국원자력연구원 Method for producing a zirconium alloy fuel cladding tube having excellent corrosion resistance by controlling the distribution of β-niobium precipitates
SE530783C2 (en) * 2007-01-16 2008-09-09 Westinghouse Electric Sweden Scatter grid for positioning fuel rods
KR100945021B1 (en) 2008-05-09 2010-03-05 한국원자력연구원 Zirconium alloy composition for nuclear fuel cladding forming protective oxide film, zirconium alloy fuel cladding manufactured using the same and method for manufacturing same
JP5629446B2 (en) * 2009-09-28 2014-11-19 株式会社東芝 REACTOR CONTROL RODS COMPOSITE, PROCESS FOR PRODUCING THE COMPOSITE AND REACTOR CONTROL RODS USING THE COMPOSITE
WO2012173738A1 (en) * 2011-06-16 2012-12-20 Westinghouse Electric Company Llc Zirconium alloys with improved corrosion/creep resistance due to final heat treatments
KR20150105343A (en) * 2013-01-11 2015-09-16 아레바 엔피 Treatment process for a zirconium alloy, zirconium alloy resulting from this process and parts of nuclear reactors made of this alloy

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US4649023A (en) * 1985-01-22 1987-03-10 Westinghouse Electric Corp. Process for fabricating a zirconium-niobium alloy and articles resulting therefrom
US5112573A (en) * 1989-08-28 1992-05-12 Westinghouse Electric Corp. Zirlo material for light water reactor applications
US5266131A (en) * 1992-03-06 1993-11-30 Westinghouse Electric Corp. Zirlo alloy for reactor component used in high temperature aqueous environment
DE59307895D1 (en) * 1993-03-04 1998-02-05 Vni Skij I Neorganiceskich Mat ZIRCON-BASED MATERIAL, PART MADE THEREOF FOR USE IN THE ACTIVE ZONE OF A NUCLEAR REACTOR AND METHOD FOR PRODUCING THIS PART
JP3564887B2 (en) * 1996-08-09 2004-09-15 三菱マテリアル株式会社 Fuel rod for light water reactor and manufacturing method thereof
US5854818A (en) * 1997-08-28 1998-12-29 Siemens Power Corporation Zirconium tin iron alloys for nuclear fuel rods and structural parts for high burnup

Also Published As

Publication number Publication date
WO2001061062A1 (en) 2001-08-23
CN1404532A (en) 2003-03-19
EP1259653A1 (en) 2002-11-27
AU2001234492A1 (en) 2001-08-27
CN1152146C (en) 2004-06-02
JP2001262260A (en) 2001-09-26
SE526648C2 (en) 2005-10-18
SE0202478D0 (en) 2002-08-19
SE0202478L (en) 2002-08-19

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