板式压水堆堆芯新型中子/热工-水力学耦合基准的单元静态耦合计算

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

Annals of Nuclear Energy Pub Date : 2025-09-23 DOI:10.1016/j.anucene.2025.111895

Zhigang Li , Junjie Pan , Shanfang Huang , Yingwei Wu , Xiafeng Zhou , Wei Lu , Bangyang Xia , Wei Zeng , Shenglong Qiang

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引用次数: 0

摘要

为了支持压水堆（PWR）中子/热工耦合（N-TH）代码的验证，中国核动力科学研究院（NPIC）与核能领域的多个研究机构合作，设计和开发了COPHP，这是一个高参数压水堆全芯中子/热工耦合基准。本文详细阐述了基准-单元明智的静态N-TH耦合的第二部分，包括案例设计，建模，结果和偏差分析。主要结论如下：1)4个参与编码（RMC/CORTH-R、OpenMC、CORCA-SPn/CORTH-R和CORCA-SPn/TH1D）的结果在32个病例中具有一致性。2)与RMC/CORTH-R相比，OpenMC的最大keff偏差为−29.6 pcm，最大单元功率加权误差（PWE）为0.185%；CORCA-SPn/CORTH-R的最大keff偏差为- 474.6 pcm，最大PWE为3.179%；CORCA-SPn/TH1D的最大keff偏差为1310.4 pcm，最大PWE为5.245%。3) COPHP-B在部分情况下核心出口的两相流显著影响了CORCA-SPn/TH1D的N-TH耦合结果。4)该基准套件为高参数pwr的高保真N-TH耦合提供了全面的结果，满足了不同的验证需求。

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Cell-wise static coupling calculation of a new neutronics/thermal-hydraulics coupling benchmark for plate-type PWR core

To support the verification of cell-wise neutronics/thermal hydraulics (N-TH) coupling codes for Pressurized Water Reactor (PWR), the Nuclear Power Institute of China (NPIC) collaborated with multiple research institutions in the nuclear energy field to design and develop COPHP, a high-parameter PWR full core cell-wise N-TH coupling benchmark. This paper elaborates on Part II of the benchmark—cell-wise static N-TH coupling—including case design, modeling, results, and deviation analysis. Key conclusions are as follows: 1) Consistency was observed among the results from four participating codes (RMC/CORTH-R, OpenMC, CORCA-SPn/CORTH-R, and CORCA-SPn/TH1D) across 32 cases covering two core configurations. 2) Compared to RMC/CORTH-R: OpenMC exhibited a maximum k_eff deviation of −29.6 pcm and a maximum cell-wise power weighting error (PWE) of 0.185 %; CORCA-SPn/CORTH-R showed a maximum k_eff deviation of −474.6 pcm and a maximum PWE of 3.179 %; CORCA-SPn/TH1D yielded a maximum k_eff deviation of 1310.4 pcm and a maximum PWE of 5.245 %. 3) Two-phase flow at the core outlet in some cases of COPHP-B significantly affected the N-TH coupling results of CORCA-SPn/TH1D. 4) This benchmark suite provides comprehensive results for high-fidelity N-TH coupling in high-parameter PWRs, catering to diverse validation needs.

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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.