Methodology for Determining the Thermal and Thermal-Stress States of a Concrete Storage Container for Spent Nuclear Fuel for Assessment of Its Service Life

Q2 Energy
S. Alyokhina, А. Kostikov, N. Smetankina, P. Gontarovskyi, N. Garmash, I. Melezhyk
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引用次数: 1

Abstract

The work is devoted to the development of methodologies for determining the thermal and thermal-stress states of the main equipment in dry container storage facilities for spent nuclear fuel. Storage facilities of this type are most common for spent fuel of nuclear power reactors. The safety of storage equipment in terms of assessing its service life is not covered widely enough in the world scientific literature. In particular, there are no effective methods for calculating the thermal and thermal-stress states of the equipment that would take into account the influence of many external factors throughout the life of a storage facility. To assess the thermal state of the containers, forward conjugate heat transfer problems, accounting for the mutual heat transfer in both a solid body and in the fluid environment (air), are proposed to be solved. Based on the solution of the conjugate heat transfer problems, the boundary conditions are to be determined to further assess the thermal-stress state of storage containers using inverse heat transfer problems. The proposed approach to determining the thermal and thermal-stress states of a concrete spent fuel container will promote more effective methods for assessing the service life of dry spent fuel storage facilities, which is, in turn, necessary in the development of ageing management programs for storage equipment and long-term safe operation.
测定用过核燃料的混凝土贮存容器的热状态和热应力状态以评估其使用寿命的方法
这项工作致力于开发用于确定乏核燃料干式容器储存设施中主要设备的热应力和热应力状态的方法。这种类型的储存设施是核反应堆乏燃料最常见的储存设施。世界科学文献对储存设备使用寿命评估的安全性覆盖范围不够广泛。特别是,没有有效的方法来计算设备的热应力和热应力状态,这些方法将考虑存储设施整个寿命期间许多外部因素的影响。为了评估容器的热状态,提出了解决前向共轭传热问题,即考虑固体和流体环境(空气)中的相互传热。在求解共轭传热问题的基础上,确定边界条件,利用反传热问题进一步评估储存容器的热应力状态。确定混凝土乏燃料容器的热应力和热应力状态的拟议方法将促进评估干乏燃料储存设施使用寿命的更有效方法,而这反过来又是制定储存设备老化管理计划和长期安全运行所必需的。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Nuclear and Radiation Safety
Nuclear and Radiation Safety Energy-Nuclear Energy and Engineering
CiteScore
0.80
自引率
0.00%
发文量
18
期刊介绍: General issues of nuclear energy use; nuclear energy (reactor theory and calculations, operation of nuclear power plants, NPP safety analysis (probabilistic safety analysis, deterministic safety analysis), research reactors, nuclear fuel and structural materials, fuel elements; neutron physics; general safety issues; decommissioning of nuclear facilities; long-term operation, spent fuel and radioactive waste management; radiation safety; I&C, physical protection.
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