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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.12
- 수록면
- 33 - 39 (7page)
이용수
초록· 키워드
오류제보하기
Generally, thermal analysis of spent fuel storage cask has been conducted using the porous media and effective thermal conductivity model to simplify the structural complexity of spent fuel assemblies. As the fuel assembly is composed of two regions; active fuel region corresponding to UO2 pellets and unactive fuel region corresponding to the top and bottom nozzle, the heat transfer performance can be influenced depending on porous media application at these regions. In this study, numerical analysis on concrete storage cask of spent fuel was performed to investigate heat transfer effects for two cases; one was porous media application only to active fuel region(case 1) and the other one was porous media to whole length of fuel assembly(case 2). Using computational fluid dynamics code, the three dimensional, 1/4 symmetry model was constructed. For two cases, maximum temperatures for each component were evaluated below the allowable limits. For the case 1, maximum temperatures for fuel cladding, neutron absorber and baskets inside the canister were slightly higher than those for the case 2. In particular, even though the helium flows with low velocity due to buoyant forces occurred at the top and bottom of unactive fuel region, treating only active fuel region as the porous media was ineffective in respect of the heat removal performance of concrete storage cask, implying a conservative result.
목차
1. 서론
2. 콘크리트 저장용기 형상 및 열전달 현상
3. 해석방법
4. 결과
5. 결론
References
참고문헌 (17)
참고문헌 신청
[기타자료] - U.S Code of Federal Regulations / 2005 / Licensing requirements for the independent storage of spent nuclear fuel and high-level radioactive waste, Part 72, title 10
[기타자료] - U.S NRC / 2010 / Standard review plan for spent fuel dry cask storage systems at a general license facility, Rev. 1
[학술지(정기간행물)] - Herranz, L.E. / 2015 / CFD analysis of a cask for spent fuel dry storage : Model fundamentals and sensitivity studies / Annals of Nuclear Energy 76 : 54 ~ 62
[학술대회논문] - In, W.K / 2014 / CFD simulation of heat and fluid flow for spent fuel in a dry storage / Transactions of Korea Nuclear Society Spring Meeting : 29 ~ 30
[학술지(정기간행물)] - Kim, H.M / 2014 / Development of scaling laws of heat removal and CFD assessment in concrete cask air path / Nuclear Engineering and Degign 278 : 7 ~ 16
[기타자료] - U.S NRC / 2010 / Standard review plan for spent fuel dry cask storage systems at a general license facility, Rev. 1
[학술지(정기간행물)] - Herranz, L.E. / 2015 / CFD analysis of a cask for spent fuel dry storage : Model fundamentals and sensitivity studies / Annals of Nuclear Energy 76 : 54 ~ 62
[학술대회논문] - In, W.K / 2014 / CFD simulation of heat and fluid flow for spent fuel in a dry storage / Transactions of Korea Nuclear Society Spring Meeting : 29 ~ 30
[학술지(정기간행물)] - Kim, H.M / 2014 / Development of scaling laws of heat removal and CFD assessment in concrete cask air path / Nuclear Engineering and Degign 278 : 7 ~ 16
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UCI(KEPA) : I410-ECN-0101-2017-559-002039731