Finding limiting rods for dry storage analyses

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Piotr Konarski, Alexey Cherezov, Cedric Cozzo, Grigori Khvostov, Hakim Ferroukhi
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引用次数: 0

Abstract

Fuel rod status during reactor operation must be numerically modeled before dry storage analyses. Simulating all the rods ever irradiated in Switzerland with state-of-the-art best estimate tools would be too time consuming. The goal of this study is to develop a methodology for identifying limiting BWR rods, where the criterion of limiting is the rod internal pressure. Limiting rods are those whose parameters may challenge rod integrity during dry storage, subsequent transport, or handling. The presence of radial hydrides is of particular importance. The precipitation of radially oriented hydrides is associated with strong tensile hoop stress of the cladding. This can be a consequence of high rod internal pressure which has been chosen the limiting parameter. In the first step, the 3D core simulators provide irradiation data. Then, the core simulator results along with rod geometrical parameters are submitted to the principal component analysis. The multidimensional datasets are reduced to 2D and processed by a clustering algorithm or not, depending on the assembly design. The limiting rods are identified for each batch or cluster and simulated with the fuel performance code Falcon and the hydrogen behavior code HYPE.
为干储存分析寻找限制棒
在进行干式贮存分析之前,必须对反应堆运行期间的燃料棒状态进行数值模拟。使用最先进的最佳估计工具模拟瑞士曾经辐照过的所有燃料棒将耗费大量时间。本研究的目标是开发一种方法,用于识别限制性生物质能反应堆燃料棒,限制性标准是燃料棒内部压力。限制性棒材是指其参数可能会在干储存、后续运输或处理过程中对棒材完整性造成挑战的棒材。径向氢化物的存在尤为重要。径向水化物的析出与包层的强拉箍应力有关。这可能是高棒内压的结果,而高棒内压被选为限制参数。第一步,三维岩心模拟器提供辐照数据。然后,将岩心模拟器结果和棒材几何参数一起提交给主成分分析。多维数据集被简化为二维数据集,并根据装配设计的不同采用聚类算法或不采用聚类算法进行处理。确定每批或每组的极限棒,并使用燃料性能代码 Falcon 和氢行为代码 HYPE 进行模拟。
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
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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