Thermal analysis of a spent fuel cask in different transport conditions

Thermal analysis of a spent fuel cask in different transport conditions
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DOI:
10.1016/j.energy.2010.01.041
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发表时间:
2011-04
期刊:
影响因子:
9
通讯作者:
R. L. Frano;G. Pugliese;G. Forasassi
R. L. Frano;G. Pugliese;G. Forasassi
中科院分区:
工程技术1区
文献类型:
--
作者:
R. L. Frano;G. Pugliese;G. Forasassi

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像所有工业一样,核电厂发电产生的废物需要管理。用于运输核材料的乏燃料元件桶必须按照严格的验收标准和标准要求设计,例如国际原子能机构的标准,以保护人类和环境免受辐射照射。这项工作的目的是评估乏燃料桶在正常和事故运输条件下的完整性,例如撞击(9米坠落到最具破坏性的平坦的水平表面上的撞击事件)和剧烈火灾事件(完全暴露在吞没的火灾中30分钟(火灾试验)或暴露在800°C的环境中进行数值模拟或炉膛试验)。利用有限元软件Ansys进行了稳态和暂态热分析,确定了燃料的最高温度和进入桶内的温度行为,考虑了桶与外部环境之间以及桶内部的所有换热模式。此外,还对车体腔内的干、湿燃料储存进行了分析。讨论了所获得的结果,用于意大利主管当局对压水堆乏燃料运输桶的新的许可批准。
Like all industries, the generation of electricity from Nuclear Power Plant produces wastes to be managed. Spent fuel element casks used for transport of nuclear materials must be designed according to rigorous acceptance criteria and standards requirements, e.g. International Atomic Energy Agency ones, in order to provide protection to people and environment against radiation exposure. The aim of this work was the evaluation of the integrity of spent fuel cask under both normal and accident transport conditions, such as impact (9m drop impact event onto a flat, essentially unyielding, horizontal surface, in the most damaging orientation) and rigorous fire events (full exposure to an engulfing fire for 30min (fire test) or to an environment at 800°C temperature for a numerical simulation or for a furnace test). Using the finite element code ANSYS both steady-state and transient thermal analyses were carried out to determine the maximum fuel temperature and the temperatures behaviour into the cask, considering all the heat transfer modes between the cask and the external environment as well as inside the cask itself. Moreover, both wet and dry fuel storage inside the cavity of the body were analyzed. The obtained results, used for the new licensing approval by the Italian competent Authority of the cask for PWR spent fuel transport, are discussed.