iPWR MELCOR模型及其在应急规划区研究中的应用

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

Nuclear Engineering and Design Pub Date : 2025-06-16 DOI:10.1016/j.nucengdes.2025.114226

John Cui, Luke Lebel, Andrew Morreale, David Hummel

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引用次数: 0

摘要

本研究提出了通用整体压水堆（iPWR）系统的MELCOR建模和分析，目的是为应急规划区（EPZ）规模的更广泛研究提供信息。iPWR设计是一种小型模块化反应堆（SMR）技术，具有很高的技术成熟度，正在考虑近期部署。为了了解对支持应急准备很重要的iPWR可能发生的事故情景/行为，本研究使用了严重事故分析代码MELCOR。选取了一个电站停电（SBO）事故作为基本情况，以及其他假定的事故情景，如蒸汽发生器给水损失、衰变排热系统故障、操作池破裂和安全壳破裂。分析调查了反应堆容器、安全壳和操作池/反应堆建筑的事故进展，以及评估案例的放射性核素释放，以提供对epz的见解。本研究中的模拟案例提供了一系列机制源项，可以适应更广泛的事故频率概率框架，从而为EPZ规模的决策提供信息。

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MELCOR model of iPWR and application to emergency planning zone study

This study presents the MELCOR modelling and analysis of a generic integral pressurized water reactor (iPWR) system with the goal of informing a broader study on emergency planning zone (EPZ) sizing. The iPWR design is one of the small modular reactor (SMR) technologies that have high technical readiness and are being considered for potential near term deployment. To understand the possible iPWR accident scenarios/behaviours important to support emergency preparedness, this study uses the severe accident analysis code MELCOR. A station blackout (SBO) accident was selected as the base case along with other postulated accident scenarios such as loss of steam generator feedwater, failure of the decay heat removal system, breaks at operating pool, and breaks in the containment vessel. The analyses investigate accident progression in the reactor vessel, containment, and operating pool/reactor building, as well as radionuclide releases for the assessed cases to provide insights on EPZs. The simulated cases in this study provide a spectrum of mechanistic source terms that can fit into the broader probabilistic framework of accident frequency that could inform decisions on EPZ sizing.

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.