Impact response analysis of cask for spent fuel by dimensional analysis and mode superposition method
Creators
- 1. Korea Institute of Nuclear Safety, Yuseong, Daejeon, Korea (Korea, Democratic People's Republic of)
- 2. Chungnam National University, Yuseong, Daejeon, Korea (Korea, Democratic People's Republic of)
Description
Full text: Full text: Due to the potentiality of accidents, the transportation safety of radioactive material has become extremely important in these days. The most important means of accomplishing the safety in transportation for radioactive material is the integrity of cask. The cask for spent fuel consists of a cask body and two impact limiters generally. The impact limiters are attached at the upper and the lower of the cask body. The cask comprises general requirements and test requirements for normal transport conditions and hypothetical accident conditions in accordance with IAEA regulations. Among the test requirements for hypothetical accident conditions, the 9 m drop test of dropping the cask from 9 m height to unyielding surface to get maximum damage becomes very important requirement because it can affect the structural soundness of the cask. So far the impact response analysis for 9 m drop test has been obtained by finite element method with complex computational procedure. In this study, the empirical equations of the impact forces for 9 m drop test are formulated by dimensional analysis. And then using the empirical equations the characteristics of material used for impact limiters are analysed. Also the dynamic impact response of the cask body is analysed using the mode superposition method and the analysis method is proposed. The results are also validated by comparing with previous experimental results and finite element analysis results. The present method is simpler than finite element method and can be used to predict the impact response of the cask
Additional details
Publishing Information
- Publisher
- Australian Nuclear Association
- Imprint Place
- Sydney (Australia)
- Imprint Title
- Book of abstracts 15"t"h Pacific basin nuclear conference
- Imprint Pagination
- 331 p.
- Journal Page Range
- p. 92
Conference
- Title
- Book of abstracts. 15. Pacific basin nuclear conference
- Dates
- 15-20 Oct 2006
- Place
- Sydney (Australia)
INIS
- Country of Publication
- Australia
- Country of Input or Organization
- Australia
- INIS RN
- 38111548
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCIDENTS; IMPACT STRENGTH; IMPACT TESTS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE DISPOSAL; REACTORS; REPUBLIC OF KOREA; SPENT FUEL CASKS; WASTE MANAGEMENT; WASTE TRANSPORTATION
- Descriptors DEC
- ASIA; CASKS; CONTAINERS; DEVELOPING COUNTRIES; MANAGEMENT; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; RADIOACTIVE WASTE MANAGEMENT; TESTING; WASTE DISPOSAL; WASTE MANAGEMENT