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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2018.1
- 수록면
- 306 - 312 (7page)
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초록· 키워드
오류제보하기
There is an increasing need in the United States and around the world to move used nuclear fuel fromwet storage in fuel pools to dry storage in casks stored at independent spent fuel storage installations orinterim storage sites. Under normal conditions, the Nuclear Regulatory Commission limits claddingtemperature to 400 C for high-burnup (>45 GWd/mtU) fuel, with higher temperatures allowed for lowburnupfuel. An analysis was conducted with FRAPCON-4.0 on three modern fuel designs with threerepresentative used nuclear fuel storage temperature profiles that peaked at 400 C. Results wererepresentative of the majority of US light water reactor fuel. They conservatively showed that hoop stressremains below 90 MPa at the licensing temperature limit. Results also show that the limiting case forhoop stress may not be at the highest rod internal pressure in all cases but will be related to the axialtemperature and oxidation profiles of the rods at the end of life and in storage
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참고문헌 (11)
참고문헌 신청
D. Lanning / 2004 / Estimated Maximum Cladding Stresses for Bounding PWR Fuel Rods during Short Term Operations for Dry Cask Storage
2003 / Interim Staff Guidance - 11, Cladding Considerations for the Transportation and Storage of Spent Fuel, Revision 3
S.R. Greene / 2013 / Storage and Transport Cask Data for Used Commercial Nuclear Fuel, ATI-TR-13047
K.J. Geelhood / 2015 / FRAPCON-4.0: a Computer Code for the Calculation of Steady-state, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup, PNNL-19417, Vol. 1 Rev. 2
K.J. Geelhood / 2013 / Used Nuclear Fuel Loading and Structural Performance under Normal Conditions of Transport - Supporting Material Properties and Modeling Inputs, FCRD-UFD-2013-20000123
2003 / Interim Staff Guidance - 11, Cladding Considerations for the Transportation and Storage of Spent Fuel, Revision 3
S.R. Greene / 2013 / Storage and Transport Cask Data for Used Commercial Nuclear Fuel, ATI-TR-13047
K.J. Geelhood / 2015 / FRAPCON-4.0: a Computer Code for the Calculation of Steady-state, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup, PNNL-19417, Vol. 1 Rev. 2
K.J. Geelhood / 2013 / Used Nuclear Fuel Loading and Structural Performance under Normal Conditions of Transport - Supporting Material Properties and Modeling Inputs, FCRD-UFD-2013-20000123
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