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A Complementary Analysis for the Structural Safety Evaluation of the Spent Nuclear Fuel Disposal Canister for the Canadian Deuterium and Uranium Reactor  

Kwon, Young-Joo (홍익대학교 기계정보공학과)
Publication Information
Journal of the Computational Structural Engineering Institute of Korea / v.22, no.5, 2009 , pp. 381-390 More about this Journal
Abstract
In this paper, a complementary analysis for the structural safety evaluation of the spent nuclear fuel disposal canister developed for the Canadian Deuterium and Uranium(CANDU) reactor for about 10,000 years long term deposition at a 500m deep granitic bedrock repository has been performed. However this developed structural model of the spent nuclear fuel disposal canister which has 33 spent nuclear fuel baskets and whose diameter is 122cm is too heavy to handle without any structural safety problem. Hence a lighter structural model of the spent nuclear fuel disposal canister which is easy to handle has been required to develop very much. There are two methods to reduce the weight of the CANDU canister model. The one is to alleviate severe design conditions such as external loads and safety factor. The other is to optimize the cross section shape of the canister by reducing the spent nuclear fuel basket number. Hence, in this paper a complementary analysis to alleviate such severe design conditions is carried out and simultaneously structural analyses to optimize the cross section shape of the canister by reducing the spent nuclear fuel basket number below 33 are carried out by varying the external load and the canister diameter for the reduction of the canister weight. The complementary analysis results show that the diameter of canister can be shortened below 122cm to reduce the weight of the spent nuclear fuel disposal canister.
Keywords
Canadian Deuterium and Uranium reactor; spent nuclear fuel disposal canister; structural safety evaluation; repository; complementary analysis; optimization;
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Times Cited By KSCI : 4  (Citation Analysis)
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