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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.1
- 수록면
- 1,079 - 1,092 (14page)
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초록· 키워드
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A parametric study of several parameters relevant to design safety on the spent nuclear fuel (SNF) rodresponse under a drop accident is presented. In the view of the complexity of interactions between theindependent safety-related parameters, a factorial design of experiment is employed as an efficientmethod to investigate the main effects and the interactions between them. A detailed single full-lengthfuel rod is used with consideration of post-irradiated fuel conditions under horizontal and vertical freedropsonto an unyielding surface using finite-element analysis. Critical drop heights and critical g-loadsthat yield the threshold plastic strain in the cladding are numerically estimated to evaluate the fuel rodstructural resistance to impact load. The combinatory effects of four uncertain parameters (pellet-claddinginterfacial bonding, material properties, spacer grid stiffness, rod internal pressure) and the interactionsbetween them on the fuel rod response are investigated. The principal finding of this researchshowed that the effects of above-mentioned parameters on the load-carrying capacity of fuel rod aresignificantly different. This study could help to prioritize the importance of data in managing andstudying the structural integrity of the SNF.
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참고문헌 (15)
참고문헌 신청
국동학 / 2013 / Review of Spent Fuel Integrity Evaluation for Dry Storage / Nuclear Engineering and Technology 45(1):115~124
U.S. Nuclear Regulatory Commission / 2010 / Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class CWaste, Rules and Regulations
U.S. Nuclear Regulatory Commission / 2009 / Packaging and Transportation of Radioactive Material, Rules and Regulations
IAEA Safety Standard / 2012 / Regulations for the safe transport of radioactive material, in: Specific Safety Requirements No. SSR-6 / IAEA
U.S. Nuclear Regulatory Commission / 2003 / Cladding considerations for the transportation and storage of spent fuel, Interim Staff Guidance-11 Rev. 3
U.S. Nuclear Regulatory Commission / 2010 / Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class CWaste, Rules and Regulations
U.S. Nuclear Regulatory Commission / 2009 / Packaging and Transportation of Radioactive Material, Rules and Regulations
IAEA Safety Standard / 2012 / Regulations for the safe transport of radioactive material, in: Specific Safety Requirements No. SSR-6 / IAEA
U.S. Nuclear Regulatory Commission / 2003 / Cladding considerations for the transportation and storage of spent fuel, Interim Staff Guidance-11 Rev. 3
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