采用两步法和超均质法对研究用反应堆进行中子学分析

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Chixu Luo, Mingrui Yang, Qing Zhu, Chaoyuan Zhang, Xiaojing Liu, Tengfei Zhang
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引用次数: 0

摘要

研究堆具有显著的中子泄漏、紧密的中子耦合和复杂的堆芯几何形状等特点,这使得使用两步法进行精确的中子计算具有挑战性。本文分析并量化了两步法在研究堆中子计算中引入的误差。以 LVR-15 研究堆为基础,通过比较计算的 keff 和功率与参考值,详细研究了几个关键因素的影响,如能量组数、均质化模型和 SN 阶数。数值结果表明,影响计算精度的因素从高到低依次为能量组数、均质化模型和 SN 顺序。能量组的数量对计算精度的影响最大。具体来说,使用过少的能量组(如 2 组能量结构)会导致对 keff 的严重高估。为了进一步提高精度,我们提出了一种改进的超均质化(SPH)方法。它能将 keff 误差稳定地保持在 500 pcm 以下,并将控制掺入和控制掺出情况下的功率预测误差分别从 3.08 ∼ 4.67 % 和 1.69 ∼ 2.80 % 降低到 1.40 ∼ 3.49 % 和 0.60 ∼ 1.98 %。这些发现为其他研究人员提供了有价值的参考指南,以实现基于两步法的更精确的研究堆中子计算。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Neutronics analysis of a research reactor using a two-step method with the superhomogenization method

Research reactors are characterized by significant neutron leakage, tight neutron coupling, and complex core geometries, which make accurate neutronics calculations using the two-step method challenging. This paper analyzes and quantifies the errors introduced by the two-step method for research reactor neutronics calculations. Based on the LVR-15 research reactor, the effects of several key factors, such as the number of energy groups, the homogenization model, and the SN order, are studied in detail by comparing the computed keff and power with reference values. The numerical results indicate that the factors affecting calculation accuracy, in descending order of impact, are the number of energy groups, the homogenization model, and the SN order. The number of energy groups has the most significant impact on calculation accuracy. Specifically, using too few energy groups, such as 2-group energy structures, leads to significant overestimations of keff. To further improve accuracy, an improved superhomogenization (SPH) method is proposed. It can stably maintain the keff error below 500 pcm and reduce power prediction errors from 3.08 ∼ 4.67 % and 1.69 ∼ 2.80 % to 1.40 ∼ 3.49 % and 0.60 ∼ 1.98 % in the control-rod-in and control-rod-out cases, respectively. These findings provide valuable reference guidelines for other researchers aiming to achieve more accurate research reactor neutronics calculations based on the two-step method.

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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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