$\require{mediawiki-texvc}$

연합인증

연합인증 가입 기관의 연구자들은 소속기관의 인증정보(ID와 암호)를 이용해 다른 대학, 연구기관, 서비스 공급자의 다양한 온라인 자원과 연구 데이터를 이용할 수 있습니다.

이는 여행자가 자국에서 발행 받은 여권으로 세계 각국을 자유롭게 여행할 수 있는 것과 같습니다.

연합인증으로 이용이 가능한 서비스는 NTIS, DataON, Edison, Kafe, Webinar 등이 있습니다.

한번의 인증절차만으로 연합인증 가입 서비스에 추가 로그인 없이 이용이 가능합니다.

다만, 연합인증을 위해서는 최초 1회만 인증 절차가 필요합니다. (회원이 아닐 경우 회원 가입이 필요합니다.)

연합인증 절차는 다음과 같습니다.

최초이용시에는
ScienceON에 로그인 → 연합인증 서비스 접속 → 로그인 (본인 확인 또는 회원가입) → 서비스 이용

그 이후에는
ScienceON 로그인 → 연합인증 서비스 접속 → 서비스 이용

연합인증을 활용하시면 KISTI가 제공하는 다양한 서비스를 편리하게 이용하실 수 있습니다.

Annealing of zirconium based articles by induction heating

IPC분류정보
국가/구분 United States(US) Patent 등록
국제특허분류(IPC7판)
  • C21D-001/00
출원번호 US-0762094 (1985-08-02)
발명자 / 주소
  • Comstock Robert J. (Penn Township
  • Westmoreland County PA) Jacobsen William A. (Burrell Township
  • Indiana County PA) Cellier Francis (Murrysville PA) Sabol George P. (Murrysville PA)
출원인 / 주소
  • Westinghouse Electric Corp. (Pittsburgh PA 02)
인용정보 피인용 횟수 : 16  인용 특허 : 11

초록

Processes for the rapid alpha annealing of zirconium based articles are described. These processes utilize induction heating to rapidly heat a worked zirconium based article to an elevated temperature after which it is then cooled. Time at the selected elevated temperature is less than about 1 secon

대표청구항

A process for alpha annealing of about 70% to about 85% cold worked Zircaloy tubing comprising the steps of: rapidly heating said cold worked Zircaloy to a temperature between about 540°and about 900°C. at a rate in excess of 800°F. per second using a scanning induction heating coil; maintaining sai

이 특허에 인용된 특허 (11)

  1. Matinlassi Ulf A. (Kennewick WA), Method and apparatus for producing zircaloy tubes and zircaloy tubes thus produced.
  2. Vesterlund Gunnar (Vsteras SEX), Method of manufacturing cladding tubes of a zirconium-based alloy for fuel rods for nuclear reactors.
  3. Vesterlund Gunnar (Vsters SEX) Anderson Erik T. (Sandviken SEX), Method of manufacturing cladding tubes of a zirconium-based alloy for fuel rods for nuclear reactors.
  4. Naylor ; Tom D. ; Matinlassi ; Ulf A., Method of producing zircaloy tubes.
  5. Eucken Craig M. (Linn County OR), Nitrogen annealing of zirconium and zirconium alloys.
  6. Armijo Joseph S. (Saratoga CA) Coffin ; Jr. Louis F. (Schenectady NY), Nuclear fuel element.
  7. Anthony Thomas R. (Schenectady NY) Cline Harvey E. (Stanford CA), Surface corrosion inhibition of zirconium alloys by laser surface b 상세보기
  • Rosenbaum Herman S. (Fremont CA) Davies John H. (San Jose CA), Thermal-mechanical treatment of composite nuclear fuel element cladding.
  • Urquhart Andrew W. (Scotia NY), Zirconium alloy heat treatment process.
  • Williams Cedric D. (Wilmington NC) Urquhart Andrew W. (Scotia NY) Walker James L. (Schenectady NY) Proebstle Richard A. (San Jose CA) Black Timothy J. (San Jose CA), Zirconium alloy heat treatment process and product.
  • Anthony Thomas R. (Schenectady NY) Cline Harvey E. (Stanford CA), Zirconium alloys having an integral b 상세보기
  • 이 특허를 인용한 특허 (16)

    1. Adamson Ronald Bert ; Lutz Daniel Reese ; Marlowe Mickey Orville ; Schardt John Frederick ; Williams Cedric David, Cladding for use in nuclear reactors having improved resistance to stress corrosion cracking and corrosion.
    2. Adamson, Ronald Bert; Lutz, Daniel Reese; Marlowe, Mickey Orville; Schardt, John Frederick; Williams, Cedric David, Cladding for use in nuclear reactors having improved resistance to stress corrosion cracking and corrosion.
    3. Spohn, Peter Dwight; Hoeck, Richard George; Sharma, Satish S., Inductively heatable components.
    4. Spohn,Peter Dwight; Hoeck,Richard George; Sharma,Satish S., Inductively heatable components.
    5. Adamson Ronald B. (Fremont CA) Potts Gerald A. (Wilmington NC), Method of fabricating zircaloy tubing having high resistance to crack propagation.
    6. White, David; Lutz, Daniel R.; Lin, Yang-Pi; Schardt, John; Potts, Gerald; Elkins, Robert; Kagami, Hiroaki; Mukai, Hideyuki, Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same.
    7. Dale Frederick Taylor, Protective coarsening anneal for zirconium alloys.
    8. Taylor Dale Frederick, Protective coarsening anneal for zirconium alloys.
    9. Ahlfeld, Charles E.; Gilleland, John Rogers; Hyde, Roderick A.; McAlees, David G.; McWhirter, Jon David; Odedra, Ashok; Tegreene, Clarence T.; Walter, Joshua C.; Weaver, Kevan D.; Whitmer, Charles; Wood, Jr., Lowell L.; Zimmerman, George B., System and method for annealing nuclear fission reactor materials.
    10. Ahlfeld, Charles E.; Gilleland, John Rogers; Hyde, Roderick A.; McAlees, David G.; McWhirter, Jon David; Odedra, Ashok; Tegreene, Clarence T.; Walter, Joshua C.; Weaver, Kevan D.; Whitmer, Charles; Wood, Jr., Lowell L.; Zimmerman, George B., System and method for annealing nuclear fission reactor materials.
    11. Ahlfeld, Charles E.; Gilleland, John Rogers; Hyde, Roderick A.; McAlees, David G.; McWhirter, Jon David; Odedra, Ashok; Tegreene, Clarence T.; Walter, Joshua C.; Weaver, Kevan D.; Whitmer, Charles; Wood, Jr., Lowell L.; Zimmerman, George B., System and method for annealing nuclear fission reactor materials.
    12. Ahlfeld, Charles E.; Gilleland, John Rogers; Hyde, Roderick A.; McAlees, David G.; McWhirter, Jon David; Odedra, Ashok; Tegreene, Clarence T.; Walter, Joshua C.; Weaver, Kevan D.; Whitmer, Charles; Wood, Jr., Lowell L.; Zimmerman, George B., System and method for annealing nuclear fission reactor materials.
    13. Ahlfeld, Charles E.; Gilleland, John Rogers; Hyde, Roderick A.; McAlees, David G.; McWhirter, Jon David; Odedra, Ashok; Tegreene, Clarence T.; Walter, Joshua C.; Weaver, Kevan D.; Whitmer, Charles; Wood, Jr., Lowell L.; Zimmerman, George B., System and method for annealing nuclear fission reactor materials.
    14. Bunel Gerard (Rugles FRX) Charquet Daniel (Albertville FRX) Dombre Max (Rugles FRX), Zircaloy 2 or Zircaloy 4 strip having specified tensile and elastic properties.
    15. White, David; Lutz, Daniel R.; Lin, Yang-Pi; Schardt, John; Potts, Gerald, Zirconium alloy fuel cladding for operation in aggressive water chemistry.
    16. Jeong, Yong Hwan; Baek, Jong Hyuk; Choi, Byoung Kwon; Lee, Myung Ho; Park, Sang Yoon; Nam, Cheol; Jung, Youn Ho, Zirconium alloy having excellent corrosion resistance and mechanical properties for nuclear fuel cladding tube.

    AI-Helper ※ AI-Helper는 오픈소스 모델을 사용합니다.

    AI-Helper 아이콘
    AI-Helper
    안녕하세요, AI-Helper입니다. 좌측 "선택된 텍스트"에서 텍스트를 선택하여 요약, 번역, 용어설명을 실행하세요.
    ※ AI-Helper는 부적절한 답변을 할 수 있습니다.

    선택된 텍스트