Process for fabricating a zirconium-niobium alloy and articles resulting therefrom
국가/구분
United States(US) Patent
등록
국제특허분류(IPC7판)
C22C-016/00
출원번호
US-0693547
(1985-01-22)
발명자
/ 주소
Sabol George P. (Murrysville Boro PA) McDonald
III Samuel G. (Monroeville PA)
출원인 / 주소
Westinghouse Electric Corp. (Pittsburgh PA 02)
인용정보
피인용 횟수 :
35인용 특허 :
11
초록▼
Articles, such as tubing, which have excellent corrosion resistance to steam at elevated temperatures and to hydriding, are produced from zirconium alloys containing 0.5 to 2.0 percent niobium, up to 1.5 percent tin, and up to 0.25 percent of a third alloying element such as iron, chromium, molybden
Articles, such as tubing, which have excellent corrosion resistance to steam at elevated temperatures and to hydriding, are produced from zirconium alloys containing 0.5 to 2.0 percent niobium, up to 1.5 percent tin, and up to 0.25 percent of a third alloying element such as iron, chromium, molybdenum, vanadium, copper, nickel and tungsten. The articles are formed by beta-treating the alloy, initially deforming the same at a temperature below 650°C. and further deforming the same through cold working stages also below 650°C., annealing the material between the cold working stages at a temperature between 500°-650°C., and final annealing the same at a temperature below 650°C. to provide articles having a microstructure of fine precipitates of less than about 800 Å, homogeneously dispersed throughout the zirconium.
대표청구항▼
An article of manufacture for use in the elevated temperature aqueous environment of a water reactor, said article comprising: a zirconium alloy comprising said article and consisting essentially of: 0.5 to 2.0 weight percent niobium, 0.9 to 1.5 weight percent tin, 0.09 to 0.11 weight percent of a t
An article of manufacture for use in the elevated temperature aqueous environment of a water reactor, said article comprising: a zirconium alloy comprising said article and consisting essentially of: 0.5 to 2.0 weight percent niobium, 0.9 to 1.5 weight percent tin, 0.09 to 0.11 weight percent of a third alloying element selected from the group consisting of iron, chromium, molybdenum, vanadium, copper, nickel and tungsten, and the balance of said alloy essentially zirconium; a microstructure of precipitates homogeneously dispersed throughout the matrix of said zirconium alloy, said precipitates having an average particle size below 800 angstroms.
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이 특허에 인용된 특허 (11)
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Matsuo Yutaka (Tokyo JPX) Suda Yoshitaka (Oyama JPX) Suda Nobuo (Omiya JPX), Highly corrosion-resistant zirconium alloy for use as nuclear reactor fuel cladding material.
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Van Swam Leonard F. P. ; Garzarolli Friedrich,DEX ; Ruhmann Heinrich,DEX, Method of manufacturing zirconium niobium tin alloys for nuclear fuel rods and structural parts for high burnup.
Van Swam Leonard F. P. ; Garzarolli Friedrich,DEX ; Ruhmann Heinrich,DEX, Method of manufacturing zirconium tin iron alloys for nuclear fuel rods and structural parts for high burnup.
Bunel Grard (Rugles FRX) Charquet Daniel (Albertville FRX) Dombre Max (Rugles FRX), Production of a strip of zircaloy 2 or zircaloy 4 in partially recrystallized state.
Jeong Yong Hwan,KRX ; Baek Jong Hyuk,KRX ; Kim Kyeong Ho,KRX ; Kim Sun-Jae,KRX ; Choi Byong Kwon,KRX ; Jung Youn Ho,KRX, Zirconium alloy having high corrosion resistance and high strength.
Barberis, Pierre; Rebeyrolle, Véronique; Hoffmann, Petra-Britt; Vermoyal, Jean-Jérôme, Zirconium alloy resistant to corrosion in drop shadows for a fuel assembly component for a boiling water reactor, component produced using said alloy, fuel assembly, and use of same.
Park, Jeong-Yong; Choi, Byoung-Kwon; Kim, Hyun Gil; Park, Sang Yoon; Jung, Yang-Il; Park, Dong Jun; Koo, Yang-Hyun, Zirconium alloys for a nuclear fuel cladding having a superior corrosion resistance by reducing an amount of alloying elements and methods of preparing a zirconium alloy nuclear fuel cladding using thereof.
Park, Jeong-Yong; Choi, Byoung-Kwon; Kim, Hyun Gil; Park, Sang Yoon; Jung, Yang-Il; Park, Dong Jun; Koo, Yang-Hyun, Zirconium alloys for a nuclear fuel cladding having a superior corrosion resistance by reducing an amount of alloying elements and methods of preparing a zirconium alloy nuclear fuel cladding using thereof.
Park, Jeong-Yong; Kim, Hyun Gil; Choi, Byoung-Kwon; Park, Sang Yoon; Jung, Yang-Il; Park, Dong Jun; Koo, Yang-Hyun, Zirconium alloys for a nuclear fuel cladding having a superior oxidation resistance in a reactor accident condition, zirconium alloy nuclear fuel claddings prepared by using thereof and methods of preparing the same.
Park, Jeong-Yong; Jung, Yang-Il; Kim, Hyun Gil; Choi, Byoung-Kwon; Park, Sang Yoon; Park, Dong Jun; Koo, Yang-Hyun, Zirconium alloys for a nuclear fuel cladding having a superior oxidation resistance in a severe reactor operation condition and methods of preparing a zirconium alloy nuclear cladding by using thereof.
Foster, John P.; Comstock, Robert J.; Atwood, Andrew; Pan, Guirong; Garde, Anand; Dahlback, Mats; Mundorff, Jonna Partezana; Mueller, Andrew J., Zirconium alloys with improved corrosion/creep resistance due to final heat treatments.
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