Group condensation method for the transport calculation of PWR with dispersed-particle fuel

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

Annals of Nuclear Energy Pub Date : 2025-08-19 DOI:10.1016/j.anucene.2025.111806

Xiang Li, Zhouyu Liu, Siyu Yi, Zhao Tian, Shunhong Wang, Longwen Jiang, Liangzhi Cao, Hongchun Wu

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引用次数: 0

Abstract

A new group condensation method for pressurized water reactor (PWR) with dispersed-particle fuel is proposed. This method utilizes the neutron current method to evaluate Dancoff correction factors for different pin-cells, after which equivalent 1-D models are built by preserving the Dancoff correction factor. The Hébert model is employed to calculate the energy spectrum of fuel particles and matrix based on the equivalent model to condense the 69-fine-group cross-sections to ∼ 20 groups. This new method can accurately evaluate the double heterogeneity effect which originates from the macro heterogeneity between fuel rods and the micro heterogeneity between particles. Verification calculations for fuel assembly and JRR-3 plate-type reactor show that this group condensation method can cut the CPU time spent on transport calculation by about 60 % while ensuring that the reactivity error is less than 65 pcm and the maximum error in assembly powers is within 1.10 % with a proper broad-group structure.

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散粒燃料压水堆输运计算的群凝结法

提出了一种适用于分散颗粒燃料压水堆的团缩新方法。该方法利用中子电流法对不同的pin-cell进行Dancoff校正因子评估，然后通过保留Dancoff校正因子建立等效的一维模型。在等效模型的基础上，采用h伯特模型计算燃料颗粒和基体的能谱，将69个细基团截面压缩到~ 20个基团。该方法能准确地评价由燃料棒间宏观非均质性和颗粒间微观非均质性引起的双重非均质效应。对燃料组件和JRR-3型板式反应堆的验证计算表明，在保证反应性误差小于65 pcm和组件功率最大误差在1.10%以内的条件下，该方法可使输运计算的CPU时间减少约60%。

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.