$\require{mediawiki-texvc}$
  • 검색어에 아래의 연산자를 사용하시면 더 정확한 검색결과를 얻을 수 있습니다.
  • 검색연산자
검색연산자 기능 검색시 예
() 우선순위가 가장 높은 연산자 예1) (나노 (기계 | machine))
공백 두 개의 검색어(식)을 모두 포함하고 있는 문서 검색 예1) (나노 기계)
예2) 나노 장영실
| 두 개의 검색어(식) 중 하나 이상 포함하고 있는 문서 검색 예1) (줄기세포 | 면역)
예2) 줄기세포 | 장영실
! NOT 이후에 있는 검색어가 포함된 문서는 제외 예1) (황금 !백금)
예2) !image
* 검색어의 *란에 0개 이상의 임의의 문자가 포함된 문서 검색 예) semi*
"" 따옴표 내의 구문과 완전히 일치하는 문서만 검색 예) "Transform and Quantization"

특허 상세정보

Zirconium alloy fuel cladding

국가/구분 United States(US) Patent 등록
국제특허분류(IPC7판) G21C-003/00   
미국특허분류(USC) 376/416 ; 376/414 ; 376/457
출원번호 US-0215453 (1994-03-21)
발명자 / 주소
출원인 / 주소
인용정보 피인용 횟수 : 15  인용 특허 : 0
초록

A cladding is provided for use in housing fissionable material in water cooled nuclear fission reactors. The cladding has inner and outer surfaces and includes (1) a cross-section of a Zirconium-based alloyed matrix, and (2) alloying elements in sufficient concentration to form precipitates disposed in the matrix. The cladding includes no more than 20 parts per million nitrogen by weight and is typically a modified Zircaloy-2 or Zircaloy-4. Metallurgically bonded to the inner region of the cladding is a zirconium barrier layer.

대표
청구항

A cladding resisting nodular corrosion while used to house fissionable material in a water cooled nuclear fission reactor, the cladding comprising inner and outer surface regions, and including a cross-section of a zirconium-based alloy matrix; and alloying elements in sufficient concentration to form precipitates disposed in the matrix, wherein the cladding includes no more than about 20 ppm nitrogen by weight.

이 특허를 인용한 특허 피인용횟수: 15

  1. Adamson Ronald B. ; Cheng Bo-Ching. Alloy for improved hydriding resistance and corrosion resistance nuclear reactor components. USP1998015712888.
  2. Van Swam Leonard F. P.. Corrosion and hydride resistant nuclear fuel rod. USP1999126005906.
  3. Bashkirtsev, Sergey Mikhailovich; Kuznetsov, Valentin Fedorovich; Kevrolev, Valery Vladimirovich; Morozov, Alexey Glebovich; Montgomery, Michael H.. Fuel assembly. USP20180610002681.
  4. Bashkirtsev, Sergey Mikhailovich; Kuznetsov, Valentin Fedorovich; Kevrolev, Valery Vladimirovich; Morozov, Alexey Glebovich; Montgomery, Michael H.. Fuel assembly. USP20180710037823.
  5. Bashkirtsev, Sergey Mikhailovich; Morozov, Alexey Glebovich; Totemeier, Aaron. Fuel assembly. USP20190110170207.
  6. Totemeier, Aaron; Bashkirtsev, Sergey M.; Morozov, Alexey G.. Fuel assembly. USP20190110192644.
  7. Nordstrom Neal C.. Functionally gradient cladding for nuclear fuel rods. USP1998015711826.
  8. Bashkirtsev, Sergey M.; Kuznetsov, Valentin F.; Kevrolev, Valery V.; Morozov, Alexey G.. Light-water reactor fuel assembly (alternatives), a light-water reactor, and a fuel element of fuel assembly. USP2016059355747.
  9. Taylor Dale Frederick. Method for determining corrosion susceptibility of nuclear fuel cladding to nodular corrosion. USP1999115991352.
  10. Uetake Naohito,JPX ; Kondoh Masayoshi,JPX ; Ohsumi Katsumi,JPX ; Maru Akira,JPX ; Asakura Yamato,JPX. Nuclear fuel rod and method of manufacturing the same. USP1998065761263.
  11. Bashkirtsev, Sergey Mikhailovich; Kuznetsov, Valentin Fedorovich; Kevrolev, Valery Vladimirovich; Morozov, Alexei Glebovich; Montgomery, Michael H.. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly. USP2014028654917.
  12. Bashkirtsev, Sergey Mikhailovich; Kuznetsov, Valentin Fedorovich; Kevrolev, Valery Vladimirovich; Morozov, Alexey Glebovich. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly. USP2012028116423.
  13. Dale Frederick Taylor. Protective coarsening anneal for zirconium alloys. USP2002036355118.
  14. Taylor Dale Frederick. Protective coarsening anneal for zirconium alloys. USP2000106126762.
  15. Chan Paul Ka-Hang,CAX. Protective coating to reduce stress corrosion cracking in zirconium alloy sheathing. USP1998095805655.