压水堆电站停电情况下蝶式止回阀建模及多因素耦合灵敏度分析

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

Annals of Nuclear Energy Pub Date : 2025-10-07 DOI:10.1016/j.anucene.2025.111906

Fulong Tang , Wei Wang , Yiming Luo

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引用次数: 0

摘要

蝶形止回阀是压水堆安全运行的重要组成部分。为了研究多因素耦合下蝶阀对冷却剂流动特性的影响，评估反应堆事故后的过程，基于MELCOR 1.8.5建立了蝶阀的物理模型，并进行了实验验证。建立了等效阀开度份额模型和等效阻力系数模型，简化了建模过程。通过敏感性分析，评价了不同建模方法对流量和事故过程的影响。此外，应用蝶式单向阀模型分析了电站停电事故时压水堆的瞬态响应。结果表明，等效阀开度模型在灵敏度分析中具有较高的精度。多因素耦合下的蝶阀模型能够准确模拟事故后情景，大大提高了计算精度。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

Modeling and multifactor coupling sensitivity analysis of butterfly check valve under the station blackout of PWR

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Modeling and multifactor coupling sensitivity analysis of butterfly check valve under the station blackout of PWR

A butterfly check valve is an important part in the safe operation of the pressurized water reactor(PWR). To study the influence of the butterfly valve on coolant flow characteristics under multi-factor coupling and evaluate the post-accident processes of the reactor, a physical model of the butterfly valve is established based on MELCOR 1.8.5 and validated by experiments. The equivalent valve opening share model and the equivalent resistance coefficient model are established to simplify the modeling process. Through sensitivity analysis, the effects of different modeling methods on flow rate and accident process are evaluated. Additionally, the butterfly check valve model is applied to analyze the transient response of the PWR during the station blackout(SBO) accident. The results show that the equivalent valve opening share model has higher accuracy in the sensitivity analysis. The butterfly valve model under multi-factor coupling enables accurate simulation of post-accident scenarios while significantly enhancing calculation accuracy.

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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.