• 제목/요약/키워드: Storage cask

검색결과 103건 처리시간 0.028초

사용후핵연료 저장용기의 지진시 활동거동 (Sliding Response of Spent Fuel Storage Cask to Earthquake)

  • 최인길;전영선
    • 한국전산구조공학회:학술대회논문집
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    • 한국전산구조공학회 1996년도 가을 학술발표회 논문집
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    • pp.70-77
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    • 1996

  • In this study, sliding response analysis of free standing structure such as multi-purpose nuclear spent fuel storage cask is peformed. The governing factors of sliding response are aspect ratio of structure and ground acceleration. The vertical acceleration component is very important factor in the sliding response of the structure. Based on the mathematical model, computer program is developed using direct forward integration method to predict the sliding response. Using the program, several parametric studies were made for sinusodial ground motion and for El Centre 1940 earthquake and Mexico 1973 earthquake. From the results, it is known that the frequency content and duration of strong motion affect the sliding of the structure.

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Thermal Analysis of a Spent Fuel Storage Cask under Normal and Off-Normal Conditions

  • Lee, J. C.;K. S. Bang;K. S. Seo;Kim, H.D.;Park, B. I.;Lee, H. Y.
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2003년도 가을 학술논문집
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    • pp.601-608
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    • 2003

  • Thermal analyses have been carried out for a spent fuel dry storage cask under normal and off-normal conditions. Environmental temperature is assumed to be $15^{\circ}C$ under the normal condition. The off-normal condition has an environmental temperature of $38^{\circ}C$. An additional off-normal condition is considered as a partial blockage of the air inlet ducts. Two of the four air inlet ducts are assumed to be completely blocked. The maximum temperatures of the fuel rod and concrete overpack were lower than the allowable values under the normal condition. Temperature distributions for the off-normal conditions were slightly higher than the normal conditions.

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Spent Fuel Dry Storage Cask Thermal Test

  • Bang, K.S.;Lee, J.C.;Seo, K.S.;Jung, K.J.;Cho, C.H.;Lee, Y.D.;Choi, B.Y.;Lee, H.Y.
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 2005년도 추계학술발표회
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    • pp.161-162
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    • 2005

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