Zirconium alloys with improved corrosion/creep resistance
원문보기
IPC분류정보
국가/구분
United States(US) Patent
등록
국제특허분류(IPC7판)
C22C-016/00
C22F-001/18
C22F-001/00
G21C-003/07
C21D-007/13
C21D-001/26
출원번호
US-0791934
(2015-07-06)
등록번호
US-10221475
(2019-03-05)
발명자
/ 주소
Foster, John P.
Comstock, Robert J.
Atwood, Andrew
Pan, Guirong
Garde, Anand
Dahlback, Mats
Mundorff, Jonna Partezana
Mueller, Andrew J.
출원인 / 주소
Westinghouse Electric Company LLC
대리인 / 주소
Spadacene, Joseph C.
인용정보
피인용 횟수 :
0인용 특허 :
49
초록▼
The invention relates to zirconium-based alloys and articles produced therefrom, such as tubing or strips, which have at least one of excellent corrosion resistance to water or steam and creep resistance at elevated temperatures in a nuclear reactor. The alloys include from about 0.2 to 1.5 weight p
The invention relates to zirconium-based alloys and articles produced therefrom, such as tubing or strips, which have at least one of excellent corrosion resistance to water or steam and creep resistance at elevated temperatures in a nuclear reactor. The alloys include from about 0.2 to 1.5 weight percent niobium, from about 0.01 to 0.6 weight percent iron, from about 0.0 to 0.8 weight percent tin, from about 0.0 to 0.5 weight percent chromium, from about 0.0 to 0.3 weight percent copper, from about 0.0 to 0.3 weight percent vanadium, and from about 0.0 to 0.1 weight percent nickel with the balance at least 97 weight percent zirconium, including impurities. Further, the articles are formed by processes that include final heat treatment of (i) SRA or PRXA (0-33% RXA), or (ii) RXA or PRXA (80-100% RXA).
대표청구항▼
1. A zirconium-based alloy having a selected one of improved corrosion resistance and improved creep resistance based on a pre-selected forming process, in an elevated temperature environment of a nuclear reactor, consisting of an alloying composition: 0.2 to 1.5 weight percent niobium;0.01 to 0.6 w
1. A zirconium-based alloy having a selected one of improved corrosion resistance and improved creep resistance based on a pre-selected forming process, in an elevated temperature environment of a nuclear reactor, consisting of an alloying composition: 0.2 to 1.5 weight percent niobium;0.01 to 0.6 weight percent iron;0.1 to 0.8 weight percent tin;0.0 to 0.5 weight percent chromium;0.0 to 0.3 weight percent copper;0.0 to 0.3 weight percent vanadium;0.0 to 0.1 weight percent nickel; anda balance at least 97 weight percent zirconium, including impurities, the zirconium-based alloy formed by a process, comprising:(a) melting the alloying composition to produce a melted alloy material;(b) forging the melted alloy material to produce a forged alloy material;(c) quenching the forged alloy material to produce a quenched alloy material;(d) extruding the quenched alloy material to produce a tube-shell alloy material;(e) pilgering the tube-shell alloy material to produce a reduced tube-shell alloy material;(f) annealing the reduced tube-shell alloy material to produce an annealed alloy material;(g) repeating steps (e) and (f) to produce a final alloy material; and(h) subjecting the final alloy material to a final heat treatment selected to provide the zirconium-based alloy exhibiting one of improved corrosion resistance and improved creep resistance,wherein for providing the zirconium-based alloy exhibiting improved corrosion resistance, the final alloy material is subjected to a final heat treatment of partial recrystallization to produce an amount of recrystallization from about 0% to about 33% with the remainder being stress relief annealed, andwherein for providing the zirconium-based alloy exhibiting improved creep resistance, the final alloy material is subjected to a final heat treatment of partial recrystallization to produce an amount of recrystallization from about 80% to about 100% recrystallization with the remainder being stress relief annealed. 2. The zirconium-based alloy of claim 1, wherein said alloy is formed into an article. 3. The zirconium-based alloy of claim 2, wherein said article is cladding. 4. The zirconium-based alloy of claim 1, wherein the alloy comprises: 0.6 to 1.5 weight percent niobium;0.01 to 0.1 weight percent iron;0.15 to 0.35 weight percent chromium;0.02 to 0.3 weight percent copper; anda balance at least 97 weight percent zirconium, including impurities. 5. The zirconium-based alloy of claim 1, wherein the alloy comprises: 0.2 to 1.5 weight percent niobium;0.25 to 0.45 weight percent iron;0.05 to 0.4 weight percent tin;0.15 to 0.35 weight percent chromium;0.01 to 0.1 weight percent nickel; anda balance at least 97 weight percent zirconium, including impurities. 6. The zirconium-based alloy of claim 1, wherein the alloy comprises: 0.4 to 1.5 weight percent niobium;0.01 to 0.1 weight percent iron;0.05 to 0.4 weight percent tin;0.0 to 0.5 weight percent chromium;0.02 to 0.3 weight percent copper;0.12 to 0.3 weight percent vanadium; anda balance at least 97 weight percent zirconium, including impurities. 7. The zirconium-based alloy of claim 6, wherein the chromium is present in an amount from 0.05 to 0.5. 8. The zirconium-based alloy of claim 1, wherein the alloy consists of: 0.4 to 1.5 weight percent niobium;0.01 to 0.3 weight percent iron;0.6 to 0.7 weight percent tin;0.0 to 0.5 weight percent chromium; anda balance at least 97 weight percent zirconium, including impurities. 9. The zirconium-based alloy of claim 8, wherein the chromium is present in an amount from 0.05 to 0.5. 10. The zirconium-based alloy of claim 1, wherein the alloy consists of: 0.4 to 1.5 weight percent niobium;0.01-0.3 weight percent iron;0.35-0.45 weight percent tin;0.0 to 0.5 weight percent chromium; anda balance at least 97 weight percent zirconium, including impurities. 11. A zirconium-based alloy in an elevated temperature environment of a nuclear reactor, consisting of an alloying composition: 0.2 to 1.5 weight percent niobium;0.01 to 0.6 weight percent iron;0.1 to 0.8 weight percent tin;0.0 to 0.5 weight percent chromium;0.0 to 0.3 weight percent copper;0.0 to 0.3 weight percent vanadium;0.0 to 0.1 weight percent nickel; anda balance at least 97 weight percent zirconium, including impurities, the zirconium-based alloy formed by a process, comprising:(a) melting the alloying composition to produce a melted alloy material;(b) forging the melted alloy material to produce a forged alloy material;(c) quenching the forged alloy material to produce a quenched alloy material;(e) rolling the quenched alloy material to produce a rolled alloy material;(f) annealing the rolled alloy material to produce a conditioned alloy material;(g) repeating steps (e) and/or (f) to produce a final alloy material; and(h) subjecting the final alloy material to a final heat treatment selected to provide the zirconium based alloy exhibiting one of improved corrosion resistance and improved creep resistance,wherein for providing the zirconium-based alloy exhibiting improved corrosion resistance, the final alloy material is subjected to a final heat treatment of partial recrystallization to produce an amount of recrystallization from about 0% to about 33% with the remainder being stress relief annealed, andwherein for providing the zirconium-based alloy exhibiting improved creep resistance, the final alloy material is subjected to a final heat treatment of partial recrystallization to produce an amount of recrystallization from about 80% to about 100% recrystallization with the remainder being stress relief annealed. 12. The zirconium-based alloy of claim 11, wherein said alloy is formed into an article. 13. The zirconium-based alloy of claim 12, wherein said article is strip. 14. The zirconium-based alloy of claim 11, wherein the forged alloy material has a rectangular cross-section. 15. A zirconium-based alloy, having one of improved corrosion resistance and improved creep resistance, in an elevated temperature environment of a nuclear reactor, consisting of: 0.4 to 1.5 weight percent niobium;0.01 to 0.3 weight percent iron;a weight percent tin weight percent tin selected from the group consisting of 0.35-0.45 and 0.6 to 0.7;0.0 to 0.5 weight percent chromium; anda balance at least 97 weight percent zirconium, including impurities.
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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.
Isobe Takeshi,JPX ; Suda Yoshitaka,JPX, Method for making Zr alloy nuclear reactor fuel cladding having excellent corrosion resistance and creep properties.
Barberis, Pierre; Simonot, Claude, Method for making a flat zirconium alloy product, resulting flat product and fuel, assembly component for nuclear power plant reactor made from said flat product.
Jeong, Yong Hwan; Baek, Jong Hyuk; Choi, Byoung Kwon; Kim, Kyeong Ho; Lee, Myung Ho; Park, Sang Yoon; Nam, Cheol; Jung, Younho, Method for manufacturing a tube and a sheet of niobium-containing zirconium alloy for a high burn-up nuclear fuel.
Jeong, Yong Hwan; Baek, Jong Hyuk; Choi, Byoung Kwon; Park, Sang Yoon; Lee, Myung Ho; Nam, Cheol; Park, Jeong Yong; Jung, Youn Ho, Method for manufacturing zirconium-based alloys containing niobium for use in nuclear fuel rod cladding.
Barberis, Pierre; Mardon, Jean-Paul; Rebeyrolle, Véronique; Aubin, Jean-Luc, Method of manufacturing a fuel cladding tube for a nuclear reactor, and a tube obtained thereby.
Mardon Jean-Paul (Caluire FRX) Sevenat Jean (Saint-Brevin-les-Pins FRX) Charquet Daniel (Ugine Cedex FRX), Method of manufacturing a tube for a nuclear fuel assembly, and tubes obtained thereby.
Barberis, Pierre; Rizzi, Noël; Robbe, Xavier, Method of producing a zirconium alloy semi-finished product for the production of elongated product and use thereof.
Foster John P. (Monroeville PA) Comstock Robert J. (Penn Township ; Westmoreland County PA) Worcester Samuel A. (Ogden UT) Sabol George P. (Export PA), Method of producing zirlo material for light water reactor applications.
Dahlbäck, Mats; Limbäck, Magnus, Method, use and device concerning cladding tubes for nuclear fuel and a fuel assembly for a nuclear boiling water reactor.
Dahlbäck,Mats; Hallstadius,Lars, Method, use and device concerning cladding tubes for nuclear fuel and a fuel assembly for a nuclear pressure water reactor.
Sabol George P. (Murrysville Boro PA) McDonald ; III Samuel G. (Monroeville PA), Process for fabricating a zirconium-niobium alloy and articles resulting therefrom.
Sabol George P. (Murrysville PA) Worcester Samuel A. (Ogden UT) Foster John P. (Monroeville PA), Process for the control of liner impurities and light water reactor cladding.
Foster John P. (Monroeville PA) Worcester Samuel A. (Butte MT) Comstock Robert J. (Penn Township ; Westmoreland County PA), Processing zirconium alloy used in light water reactors for specified creep rate.
Mardon Jean-Paul (Caluire FRX) Charquet Daniel (Albertville FRX) Perez Marc (Levallois FRX) Senevat Jean (Saint Brevin les Pins FRX), Rod for a fuel assembly of a nuclear reactor resisting corrosion and wear.
Lunde Liv (Nittedal NOX) Asher Raymond C. (Newbury GB2) Slattery Gerard (Leatown ; Nr. Preston GB2) Trowse Frank W. (Preston GB2) Tyzack Christopher (Hale Barns GB2) stberg Gustaf C. (Stockholm SEX) , Zirconium alloys.
Fujieda Tadashi,JPX ; Inagaki Masahisa,JPX ; Takase Iwao,JPX ; Nakajima Junjiro,JPX ; Asano Rinichi,JPX ; Seto Takehiro,JPX, Zirconium based alloy of low irradiation growth, method of producing the same, and use of the same.
Nikulina Antonina V. (Moscow RUX) Markelov Pavel P. (Moscow RUX) Markelov Vladimir A. (Moscow RUX) Peregud Mikhail M. (Moscow RUX) Ivanov Anatoly N. (Moscow RUX) Shebaldov Pavel V. (Moscow RUX) Losit, Zirconium-based material, products made from said material for use in the nuclear reactor core, and process for producin.
Foster John P. (Monroeville PA) Comstock Robert J. (Penn Township ; Westmoreland County PA) Worcester Samuel A. (Butte MT) Sabol George P. (Export PA), Zirlo material for light water reactor applications.
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