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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2014.1
- 수록면
- 681 - 688 (8page)
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Hydride reorientation behaviors of PWR cladding tubes under typical interim dry storage conditions were investigatedwith the use of as-received 250 and 485ppm hydrogen-charged Zr-Nb alloy cladding tubes. In order to evaluate theeffect of typical cool-down processes on the radial hydride precipitation, two terminal heat-up temperatures of 300 and400ºC, as well as two terminal cool-down temperatures of 200 and 300ºC, were considered. In addition, two cooling ratesof 2.5 and 8.0ºC/min during the cool-down processes were taken into account along with zero stress or a tensile hoopstress of 150MPa. It was found that the 250ppm hydrogen-charged specimen experiencing the higher terminal heat-uptemperature and the lower terminal cool-down temperature generated the highest number of radial hydrides during thecool-down process under 150MPa hoop tensile stress, which may be explained by terminal solid hydrogen solubilities forprecipitation, and dissolution and remaining circumferential hydrides at the terminal heat-up temperatures. In addition, theslower cool-down rate generates the larger number of radial hydrides due to a cooling rate-dependent, longer residencetime at a relatively high temperature that can accelerate the radial hydride nucleation and growth.
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참고문헌 (21)
참고문헌 신청
A. Colas / 2010 / In-situ Study of Hydride Precipitation Kinetics and Re-orientation in Zircaloy Using Synchrotron Radiation / Acta Mater 58 : 6575 ~
A. Varias / 2000 / Simulation of Hydrogen Embrittlement in Zirconium Alloys under Stress and Temperature Gradients / J. Nucl. Mater 279 : 273 ~ 285
B. Cox / 1999 / A Hydrogen Uptake Micro-mechanism for Zr alloys / J. Nucl. Mater 270 : 134 ~ 146
B. Kammenzind / 1995 / Hydrogen Pickup and Redistribution in Alpha-Annealed Zircaloy-4 / International Symposium on Zirconium in the Nuclear Industry : 338 ~
G. Bertolino / 2003 / Effects of Hydrogen Content and Temperature on Fracture Toughness of Zircaloy-4 / J. Nucl. Mater 320 : 272 ~ 279
A. Varias / 2000 / Simulation of Hydrogen Embrittlement in Zirconium Alloys under Stress and Temperature Gradients / J. Nucl. Mater 279 : 273 ~ 285
B. Cox / 1999 / A Hydrogen Uptake Micro-mechanism for Zr alloys / J. Nucl. Mater 270 : 134 ~ 146
B. Kammenzind / 1995 / Hydrogen Pickup and Redistribution in Alpha-Annealed Zircaloy-4 / International Symposium on Zirconium in the Nuclear Industry : 338 ~
G. Bertolino / 2003 / Effects of Hydrogen Content and Temperature on Fracture Toughness of Zircaloy-4 / J. Nucl. Mater 320 : 272 ~ 279
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