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适用于高通量堆的一步法计算方法研究与应用

薛鹏超 张乾 张晋超 赵强 曹巍 谢楚涛

原子能科学技术2025,Vol.59Issue(5):1064-1074,11.
原子能科学技术2025,Vol.59Issue(5):1064-1074,11.DOI:10.7538/yzk.2024.youxian.0937

适用于高通量堆的一步法计算方法研究与应用

Research and Application of One-step Computational Method for High Flux Reactor

薛鹏超 1张乾 2张晋超 1赵强 1曹巍 2谢楚涛2

作者信息

  • 1. 哈尔滨工程大学核科学与技术学院核安全与仿真技术国防重点实验室,黑龙江 哈尔滨 150001
  • 2. 浙江大学物理学院浙江近代物理中心先进核能理论与应用实验室,浙江 杭州 310058
  • 折叠

摘要

Abstract

High flux reactors,as versatile irradiation facilities,have significant applications in various fields such as neutron scattering research,isotope production,and material irradiation testing.However,due to their unique design,different regions of the core exhibit markedly different energy spectrum characteristics.At the same time,two-dimensional full-core-scale high-order transport calculations require a large amount of memory.Therefore,due to current hardware limitations,it is not feasible to perform full-core-scale high-order transport calculations based on ultra-fine group structures.To address these issues,this paper proposes a one-step calculation scheme with online energy group condensation suitable for high flux reactors.In this paper,firstly,an ultra-fine group structure of 2165 groups was selected to complete resonance calculations on fine geometric modeling.Secondly,combined with the low-order scattering source term approximation,only a few source iteration calculations were performed to obtain the low-order approximate flux.Then,the low-order approximate flux and the ultra-fine group total cross-sections were used to calculate the approximate high-order flux and complete the multi-group high-order cross-section condensation.Finally,the high-order approximate flux and multi-group high-order cross-sections were used for multi-group high-order calculations to obtain eigenvalue information and flux distribution information.The method based on two high flux reactor designs was verified and the sensitivity of the selected multi-group energy structure to this calculation scheme was analyzed.The calculation results show that under the 172 group structure,the eigenvalue deviations obtained by using this calculation scheme for the two core designs are both below 136 pcm.At the same time,it can be seen that in this test problem,the fast/thermal neutron flux distribution and flux density peaks are insensitive to the energy group structure,and the relative errors of the fast/thermal neutron flux density peaks for both core designs are below 1.5%.The calculation accuracy of the irradiation channel flux shape is related to the energy group structure and the properties of the materials themselves.In this test,the relative errors of most group fluxes are below 5%.Based on this,it can be seen that the calculation scheme proposed in this paper can effectively solve the memory limitation problem in two-dimensional full-core-scale high-order transport calculations and is suitable for neutron numerical simulation calculations in high flux reactors with high computational accuracy.

关键词

高通量堆/在线能群归并/确定论计算/超细群/共振计算/高阶通量近似

Key words

high flux reactor/online energy group condensation/deterministic calculation/ultra-fine group/resonance calculation/high-order flux approximation

分类

能源科技

引用本文复制引用

薛鹏超,张乾,张晋超,赵强,曹巍,谢楚涛..适用于高通量堆的一步法计算方法研究与应用[J].原子能科学技术,2025,59(5):1064-1074,11.

基金项目

国家自然科学基金(12105063) (12105063)

原子能科学技术

OA北大核心

1000-6931

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