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Spent fuel transport cask thermal evaluation under normal and accident conditions

机译:正常和事故情况下用过的燃料运输桶的热评估

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The casks used for transport of nuclear materials, especially the spent fuel element (SPE), must be designed according to rigorous acceptance criteria and standards requirements, e.g. the International Atomic Energy Agency ones, in order to provide protection to people and environment against radiation exposure particularly in a severe accident scenario.rnThe aim of this work was the evaluation of the integrity of a spent fuel cask under both normal and accident scenarios transport conditions, such as impact and rigorous fire events, in according to the IAEA accident test requirements. The thermal behaviour and the temperatures distribution of a Light Water Reactor (LWR) spent fuel transport cask are presented in this paper, especially with reference to the Italian cask designed by AGN, which was characterized by a cylindrical body, with water or air inside the internal cavity, and two lateral shock absorbers.rnUsing the finite element code ANSYS a series of thermal analyses (steady-state and transient thermal analyses) were carried out in order to obtain the maximum fuel temperature and the temperatures field in the body of the cask, both in normal and in accidents scenario, considering all the heat transfer modes between the cask and the external environment (fire in the test or air in the normal conditions) as well as inside the cask itself.rnIn order to follow the standards requirements, the thermal analyses in accidents scenarios were also performed adopting a deformed shape of the shock absorbers to simulate the mechanical effects of a previous IAEA 9 m drop test event. Impact tests on scale models of the shock absorbers have already been conducted in the past at the Department of Mechanical, Nuclear and Production Engineering, University of Pisa, in the '80s. The obtained results, used for possible new licensing approval purposes by the Italian competent Authority of the cask for PWR spent fuel cask transport by the Italian competent Authority, are discussed.
机译:用于运输核材料,特别是乏燃料元件(SPE)的桶必须根据严格的验收标准和标准要求进行设计,例如:国际原子能机构,以保护人类和环境免受辐射照射,特别是在严重事故情况下。这项工作的目的是评估正常和事故情况下运输条件下乏燃料桶的完整性。根据国际原子能机构(IAEA)事故测试要求,例如撞击和严峻的火灾。本文介绍了轻水反应堆(LWR)乏燃料运输桶的热行为和温度分布,特别是参考了AGN设计的意大利桶,该桶的特征是圆柱体,内部装有水或空气。内腔和两个侧向减震器。使用有限元代码ANSYS进行了一系列热分析(稳态和瞬态热分析),以便获得最高的燃料温度和罐体内的温度场在正常和意外情况下,都考虑到容器与外部环境之间的所有传热模式(测试中的火或正常条件下的空气)以及容器本身内部。为了遵守标准要求,事故场景中的热分析也采用了变形的减震器进行,以模拟先前国际原子能机构9 m跌落时的机械作用。 st事件。过去在80年代,比萨大学机械,核与生产工程系已经对减震器的比例模型进行了冲击试验。对获得的结果进行了讨论,该结果将用于意大利主管当局的压水堆乏燃料桶运输的意大利主管当局用于可能的新许可证审批目的的罐体。

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