Dynamic response characteristics of DHRS in small pressurized water reactor under SGTR accident

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

Annals of Nuclear Energy Pub Date : 2025-09-27 DOI:10.1016/j.anucene.2025.111900

Xiaojun Qiu , Xiangbin Li , Yusheng Liu , Chengshen Wang , Dechen Zhang

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Abstract

Small modular reactors (SMRs) are considered a promising direction for the future development of nuclear power generation due to their enhanced safety, lower initial costs, shorter construction periods, and flexible deployment options. Some typical reactors ensure robust performance during both normal operation and accident scenarios by employing passive safety mechanisms. To further understand the capabilities of these passive safety systems, based on the NuScale integral pressurized water reactor, a simulation model was developed using RELAP5 code to analyze the thermal–hydraulic response characteristics of the decay heat removal system (DHRS) during a steam generator tube rupture (SGTR) accident. The results show that the decay heat removal heat exchanger (DHRHX) can eliminate the core decay heat and effectively control the core inlet and outlet temperatures. When the water level in the primary loop drops below the baffle of the pressurizer, significant flow oscillations will occur, triggering fluctuations in other parameters.

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SGTR事故下小型压水堆DHRS动态响应特性

小型模块化反应堆（SMRs）被认为是未来核能发电发展的一个有前途的方向，因为它具有更高的安全性、更低的初始成本、更短的建设周期和灵活的部署选择。一些典型的反应堆通过采用被动安全机制来保证在正常运行和事故情况下的稳健性能。为了进一步了解这些被动安全系统的能力，基于NuScale整体式压水堆，利用RELAP5代码建立了仿真模型，分析了蒸汽发生器管破裂（SGTR）事故中衰变排热系统（DHRS）的热-水力响应特性。结果表明，衰减消热换热器（DHRHX）能够消除堆芯衰减热，有效控制堆芯进出口温度。当主回路的水位降到稳压器挡板以下时，会发生明显的流量振荡，从而引发其他参数的波动。

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.