DONJON5/CLASS coupled simulations of MOX/UO2 heterogeneous PWR core

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY
Maxime Paradis, X. Doligez, G. Marleau, M. Ernoult, N. Thiollière
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引用次数: 2

Abstract

Most fuel cycle simulation tools are based either on fixed recipes or assembly calculations for reactor modeling. Due to the high number of calculations and extensive computational power requirements, full-core computations are often seen as not viable for this purpose. However, this leads to additional hypotheses and modeling biases, thus limiting the realism of the resulting fuel cycle. For several applications, the current modeling method is sufficient, but precise calculations of discharged fuel composition may require further refinements. CLASS (Core Library for Advanced Simulation Scenarios) is a dynamic fuel cycle simulation code developed since 2012 with reactor models based on neural networks to produce nuclear data and physical quantities. Past work has shown a first coupling between CLASS and DONJON5 to quantify neural networks approach biases. This work assesses the applicability of 3D full-core diffusion calculations using the DONJON5 code coupled with nuclear scenario simulations involving a realistic PWR core at equilibrium cycle conditions. DONJON5 interpolates burnup dependent diffusion coefficients and cross sections generated beforehand by DRAGON5, a deterministic lattice calculation tool. Whereas previous studies considered only homogeneous reactors (i.e. homogeneous assembly in terms of composition and enrichment as well as homogeneous core), the present contribution focuses on the integration of full-core calculations in CLASS for fuel cycles involving a MOX/UO2 PWR core (i.e. 1/3 MOx–2/3 UOx). The DONJON5 model considered in this work describes a core with critical boron concentration at each time step partially loaded with MOx heterogeneous assemblies composed of three enrichments. In fuel cycle calculations, the main issue is to adapt, in the fabrication stage, the fresh fuel composition for the reactor with regards to the isotopic composition of the available stocks. This work presents a fuel loading model based on power peaking factors minimization that respects irradiation cycle length, 235U enrichment as well as Pu concentration and fissile quality, hence, ensuring a more uniform power distribution in the core.
MOX/UO2非均质压水堆堆芯的DONJON5/CLASS耦合模拟
大多数燃料循环模拟工具要么基于固定配方,要么基于反应堆建模的装配计算。由于大量的计算和广泛的计算能力需求,全核计算通常被认为是不可行的。然而,这会导致额外的假设和建模偏差,从而限制了最终燃料循环的真实性。对于一些应用,目前的建模方法是足够的,但排放燃料成分的精确计算可能需要进一步的改进。CLASS(高级模拟场景核心库)是自2012年以来开发的动态燃料循环模拟代码,基于神经网络的反应堆模型,用于生成核数据和物理量。过去的研究表明,CLASS和DONJON5之间的首次耦合可以量化神经网络方法的偏差。这项工作评估了3D全堆扩散计算的适用性,使用DONJON5代码结合核情景模拟,包括一个现实的压水堆堆芯在平衡循环条件下。DONJON5插值了由确定性晶格计算工具DRAGON5事先生成的与燃耗相关的扩散系数和截面。以前的研究只考虑了均质反应堆(即在组成和富集方面均质装配以及均质堆芯),而目前的贡献侧重于在CLASS中集成涉及MOX/UO2压水堆堆芯(即1/3 MOX - 2/3 UOx)的燃料循环的全堆计算。本工作中考虑的DONJON5模型描述了在每个时间步具有临界硼浓度的核心,部分装载由三种富集组成的MOx非均相组件。在燃料循环计算中,主要问题是在制造阶段使反应堆的新鲜燃料成分与可用燃料的同位素组成相适应。本文提出了一种基于功率峰值因子最小化的燃料加载模型,该模型考虑了辐照周期长度、235U富集、Pu浓度和裂变质量,从而确保了堆芯中更均匀的功率分布。
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
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
20.00%
发文量
18
审稿时长
10 weeks
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