Advancements to generalized equivalence theory for preserving cross-sections of whole core simulations

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Oscar Lastres, Yunlin Xu
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Abstract

The conventional two-step approach, without the use of an equivalence method, can introduce significant error for the simulation of non-LWRs (Light Water Reactors), especially fast reactors, due to the large leakage and high anisotropic neutron distribution. To improve upon the accuracy of the two-step approach, a 3D whole core model is simulated with a transport method to generate region-wise homogenized cross-sections (XS). These XS can then be used in a diffusion whole core solver during the second step to extend the application to cycle and transient analysis. Discontinuity factors (DFs) are then introduced to improve the accuracy during the simulation of the second step. With properly generated DFs from Generalized Equivalence Theory (GET), the region-averaged solutions from the first transport step can then be reproduced by the second step diffusion solver. The Monte Carlo method was selected to perform the whole core transport simulation to generate region-wise XS. However, simulating whole core problems with Monte Carlo may result in poor statistics near the peripheral region especially for partial current tallies. This paper introduces an advancement to GET to reproduce region-wise solutions for select regions when the reaction rates and surface currents have good statistics in these regions but poor statistics in other regions. A reference high-fidelity model was constructed using the Serpent 2 Monte Carlo code based on the EBR-II benchmark evaluation and verification was carried out using the TriPEN-4 method in PARCS. The results show that it is possible to reproduce the exact eigenvalue and power distributions of whole core problems in a feasible manner.
用于保存整个岩心模拟截面的广义等价理论的进展
由于存在大量泄漏和各向异性的中子分布,不使用等效方法的传统两步法会给非轻水反应堆(尤其是快堆)的模拟带来很大误差。为了提高两步法的精确度,采用传输方法对三维全堆芯模型进行模拟,以生成区域均匀化截面(XS)。在第二步中,这些 XS 可用于扩散整个岩心求解器,从而将应用扩展到循环和瞬态分析。然后引入不连续因子 (DF),以提高第二步模拟的精度。有了根据广义等效理论(GET)正确生成的 DF,第二步扩散求解器就可以再现第一步传输过程中的区域平均解。我们选择蒙特卡洛方法来进行整个岩心的传输模拟,以生成区域 XS。然而,用蒙特卡罗法模拟整个岩心问题可能会导致外围区域附近的统计数据较差,尤其是部分电流统计。本文介绍了 GET 的一种改进方法,即当反应速率和表面电流在选定区域的统计量较好,而在其他区域的统计量较差时,在这些区域重现区域解。在 EBR-II 基准评估的基础上,使用 Serpent 2 蒙地卡罗代码构建了一个参考高保真模型,并使用 PARCS 中的 TriPEN-4 方法进行了验证。结果表明,有可能以可行的方式再现整个核心问题的精确特征值和功率分布。
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
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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