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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.10
- 수록면
- 3,379 - 3,397 (19page)
- DOI
- https://doi.org/10.1016/j.net.2021.04.025
이용수
초록· 키워드
오류제보하기
In this study, a multi-physics modeling method was developed to analyze a nuclear fuel rod's thermomechanical behavior especially for high temperature anisotropic creep deformation during ballooningand burst occurring in Loss of Coolant Accident (LOCA). Based on transient heat transfer and nonlinearmechanical analysis, the present work newly incorporated the nuclear fuel rod's special characteristicswhich include gap heat transfer, temperature and burnup dependent material properties, and especiallyfor high temperature creep with material anisotropy. The proposed method was tested through variousbenchmark analyses and showed good agreements with analytical solutions. From the validation studywith a cladding burst experiment which postulates the LOCA scenario, it was shown that the presentdevelopment could predict the ballooning and burst behaviors accurately and showed the capability topredict anisotropic creep behavior during the LOCA. Moreover, in order to verify the anisotropic creepmethodology proposed in this study, the comparison between modeling and experiment was made withisotropic material assumption. It was found that the present methodology with anisotropic creep couldpredict ballooning and burst more accurately and showed more realistic behavior of the cladding.
목차
등록된 정보가 없습니다.
참고문헌 (39)
참고문헌 신청
W. Wen / 2018 / Mechanism-based modeling of solutestrengthening : application to thermal creep in Zr alloy / Int. J. Plast 106:88~106
G. S. Was / 2019 / Materials for future nuclear energy systems / J. Nucl. Mater 527:151837
P. Van Uffelen / 2019 / A review of fuel performance modelling / J. Nucl. Mater 516:373~412
K. Geelhood / 2011 / FRAPTRAN 1.4: A Computer Code for the Transient Analysis of Oxide Fuel Rods :1
R. Williamson / 2012 / Multidimensional multiphysics simulation of nuclear fuel behavior / J. Nucl. Mater 423:149~163
G. S. Was / 2019 / Materials for future nuclear energy systems / J. Nucl. Mater 527:151837
P. Van Uffelen / 2019 / A review of fuel performance modelling / J. Nucl. Mater 516:373~412
K. Geelhood / 2011 / FRAPTRAN 1.4: A Computer Code for the Transient Analysis of Oxide Fuel Rods :1
R. Williamson / 2012 / Multidimensional multiphysics simulation of nuclear fuel behavior / J. Nucl. Mater 423:149~163
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