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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2017.1
- 수록면
- 1,740 - 1,747 (8page)
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To investigate allowable peak cladding temperature and hoop stress for maintenance of cladding integrity during interim-dry storage and subsequent transport, zirconium alloy cladding tubes were hydrogen-charged to generate 250 ppm and 500 ppm hydrogen contents, simulating spent nuclear fuel degradation. The hydrogen-charged specimens were heated to four peak temperatures of 250℃, 300℃, 350℃, and 400℃, and then cooled to room temperature at cooling rates of 0.3 ℃/min under three tensile hoop stresses of 80 MPa, 100 MPa, and 120 MPa. The cool-down specimens showed that high peak heatup temperature led to lower hydrogen content and that larger tensile hoop stress generated larger radial hydride fraction and consequently lower plastic elongation. Based on these out-of-pile cladding tube test results only, it may be said that peak cladding temperature should be limited to a level < 250℃, regardless of the cladding hoop stress, to ensure cladding integrity during interim-dry storage and subsequent transport.
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참고문헌 (19)
참고문헌 신청
D. Northwood / 1983 / Hydrides and delayed hydrogen cracking in zirconium and its alloys / Int. Met. Rev 28 : 92 ~ 121
G. Itoh / 1999 / Embrittlement in an agehardened 2091 aluminum alloy by exposure at elevated temperatures below the aging temperature / Acta Mater 47 : 3799 ~ 3809
H. Chung / 2000 / Fundamental metallurgical aspects of axial splitting in Zircaloy cladding / Proc. Int. Topical Meeting on Light Water Reactor Fuel Performance : 325 ~
J. Kearns / 1966 / Effect of texture, grain size, and cold work on the precipitation of oriented hydrides in Zircaloy tubing and plate / J. Nucl. Mater 20 : 241 ~ 261
K. Colas / 2010 / In situ study of hydride precipitation kinetics and reorientation in Zircaloy using synchrotron radiation / Acta Mater 58 : 6575 ~ 6583
G. Itoh / 1999 / Embrittlement in an agehardened 2091 aluminum alloy by exposure at elevated temperatures below the aging temperature / Acta Mater 47 : 3799 ~ 3809
H. Chung / 2000 / Fundamental metallurgical aspects of axial splitting in Zircaloy cladding / Proc. Int. Topical Meeting on Light Water Reactor Fuel Performance : 325 ~
J. Kearns / 1966 / Effect of texture, grain size, and cold work on the precipitation of oriented hydrides in Zircaloy tubing and plate / J. Nucl. Mater 20 : 241 ~ 261
K. Colas / 2010 / In situ study of hydride precipitation kinetics and reorientation in Zircaloy using synchrotron radiation / Acta Mater 58 : 6575 ~ 6583
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