Neutronics calculation and analysis of a small lead-bismuth fast reactor core with control rods integrated within fuel assemblies

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-06-13 DOI:10.1016/j.anucene.2025.111653

Jiehao Gao, Haoyu Fan, Xianan Du, Wenjie Chen, Youqi Zheng

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引用次数: 0

Abstract

The small lead–bismuth fast reactor with control rods integrated within fuel assemblies, represented by Russia’s SVBR-100 reactor, places control rods directly into the center of fuel assemblies to achieve a compact and space-saving design. This approach poses several challenges for reactor neutronics codes compared with traditional fast reactor design. To address these challenges, this study further develops the SARAX neutron physics analysis code system to meet the core neutronics calculation requirements of small lead–bismuth reactors with in-assembly control rods. To verify the computational accuracy of the code, this paper establishes a computational model for this type of reactor core to perform burnup calculations and fine rods power calculations for the entire life. The results show that the SARAX program exhibits high computational accuracy in both criticality calculations and fine rods power calculations, indicating that the code meets the neutronics calculation requirements for this type of reactor core.

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燃料组件内集成控制棒的小型铅铋快堆堆芯的中子计算与分析

小型铅铋快堆的控制棒集成在燃料组件中，以俄罗斯的SVBR-100反应堆为代表，将控制棒直接放置在燃料组件的中心，以实现紧凑和节省空间的设计。与传统的快堆设计相比，这种方法对反应堆中子码提出了一些挑战。为了解决这些挑战，本研究进一步开发了SARAX中子物理分析代码系统，以满足具有装配控制棒的小型铅铋堆的堆芯中子计算要求。为了验证程序的计算准确性，本文建立了该型堆芯的计算模型，进行了全寿命的燃耗计算和细棒功率计算。结果表明，SARAX程序在临界计算和细棒功率计算中均具有较高的计算精度，满足该类堆芯的中子计算要求。

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 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.