Verification of the reactor core sub-channel thermal hydraulic analysis code: CORTH under the flow transient conditions

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-05-10 DOI:10.1016/j.anucene.2025.111538

Xiaoyu Wang , Shinian Peng , Jian Deng , Yu Liu , Sichao Tan , Jiageng Wang , Wei Zeng , Xue Zhang

引用次数: 0

Abstract

The resistance characteristics of the reactor core will change under flow transient conditions. So, it is necessary to conduct verification and validation research on the core sub-channel code under flow transient conditions. Firstly, sub-channel analysis code CORTH is briefly introduced, and then CORTH is validated based on rod bundle pressure drop experiment. The verification and validation results indicate that the code is in good agreement with the experimental results. For the rod bundle channel bare rod area, the deviation between the calculated pressure drop and the experimental measured pressure drop is less than 6%. For the spacer grid area, the deviation between the calculated pressure drop and the measured pressure drop is mostly less than 8%. The validated CORTH can be used to analyze and calculate the resistance characteristics of the core under flow transient conditions.

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核反应堆堆芯子通道热工分析代码验证：CORTH在流动瞬态条件下

在流动暂态条件下，电抗器堆芯的电阻特性会发生变化。因此，有必要对流动瞬态条件下的核心子通道代码进行验证和验证研究。首先简要介绍了子通道分析代码CORTH，然后基于杆束压降实验对CORTH进行了验证。验证和验证结果表明，该代码与实验结果吻合较好。对于棒束通道裸棒区域，计算压降与实验实测压降的偏差小于6%。对于间隔栅区域，计算压降与实测压降的偏差大多小于8%。验证后的CORTH可用于分析和计算流动瞬态条件下铁心的电阻特性。

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.