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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2009.1
- 수록면
- 171 - 178 (8page)
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초록· 키워드
오류제보하기
The rate of delayed hydride cracking (DHC), V, has been measured in cold-worked and stress-relieved Zircaloy-4 fuel
cladding using the Pin-Loading Tension technique. At 250 °C the mean value of V from 69 specimens was 3.3(±0.8)x10⁻⁸ m/s
while the temperature dependence up to 275 °C was described by Aexp(-Q/RT), where Q is 48.3 kJ/mol. No cracking or
cracking at very low rates was observed at higher temperatures. The fracture surface consisted of flat fracture with no striations.
The results are compared with previous results on fuel cladding and pressure tubes.
목차
등록된 정보가 없습니다.
참고문헌 (20)
참고문헌 신청
A. Sawatzky / 1960 / The Diffusivity and Solubility of Hydrogen in the Alpha-phase of Zircaloy / J. Nuclear Materials 2 : 62 ~ 68
A. Sawatzky / 1981 / Hydrogen Diffusion in Zirconium-Niobium Alloys / Proc. International Symposium on Metal-Hydrogen Systems : 109 ~ 120
C. E. Coleman / 2008 / Measurement of Rates of Delayed Hydride Cracking (DHC) in Zr-2.5Nb ? An IAEA Coordinated Research Project / J. ASTM International 5 (2) : 101091 ~
D. Schrire / 1994 / Secondary Defect Behaviour in ABB BWR Fuel / Proc. International Topical Meeting on Light Water Reactor Fuel Performance : 398 ~ 409
E. C. W. Perryman / 1978 / Pickering Pressure Tube Cracking Experience / Nuclear Energy 17 : 95 ~ 105
A. Sawatzky / 1981 / Hydrogen Diffusion in Zirconium-Niobium Alloys / Proc. International Symposium on Metal-Hydrogen Systems : 109 ~ 120
C. E. Coleman / 2008 / Measurement of Rates of Delayed Hydride Cracking (DHC) in Zr-2.5Nb ? An IAEA Coordinated Research Project / J. ASTM International 5 (2) : 101091 ~
D. Schrire / 1994 / Secondary Defect Behaviour in ABB BWR Fuel / Proc. International Topical Meeting on Light Water Reactor Fuel Performance : 398 ~ 409
E. C. W. Perryman / 1978 / Pickering Pressure Tube Cracking Experience / Nuclear Energy 17 : 95 ~ 105
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