ASTEC validation of SFP dewatering using results from the DENOPI project

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-02-21 DOI:10.1016/j.anucene.2025.111249
Laurent Laborde, Benoît Migot
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Abstract

Loss of cooling in a Spent Fuel Pool (SFP) of a nuclear power plant can lead to the melting of fuel assemblies and to strong radiological consequences to the environment. In order to study the first phases of such accidents, up to the fuel assemblies uncovery, the DENOPI project was launched by the French Institute for Radiation Protection and Nuclear Safety (IRSN1) supported and funded by the French Government and partners. Among the different facilities developed in the project, the MIDI facility aims at studying the complex thermal-hydraulics phenomena occurring in a large water pool heated from the bottom by electrical rods arranged in dedicated racks. MIDI is scaled by homothety to a typical French SFP. Different assembly arrangements (loading patterns) have been tested at different power levels, with either uniform power repartition, or hot and cold cells. In each test, the water level and temperatures at different elevations are followed, as well as mass flow rate entering each fuel rack. These experimental results also provide relevant data for the analysis and understanding of large natural convection loops that are expected in immersed passive heat removal systems of Small Modular Reactors. The forthcoming OECD/NEA POLCA project aims to extend such results database, in particular to assess the capability of thermal-hydraulics codes to reproduce the main tendencies of these experimental results.
The ASTEC code developed by IRSN is a system code dedicated to the simulation of major accidents in nuclear facilities that may lead to the release of radiological material. Recent works within the MUSA European project have shown the importance of reducing models uncertainties in the first phases of the accident, during the pool dewatering. In this paper, first simulations of MIDI tests are performed with ASTEC in order to assess and improve the capability of ASTEC to simulate the dewatering of a large water pool such as a SFP during a loss-of-cooling accident. Simulations are performed for a selection of MIDI tests with different heating patterns and power levels. Different models of subcooled boiling models from the literature are tested in ASTEC, stressing the key role of these models for an accurate prediction of the experimental flow.
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使用DENOPI项目的结果对SFP脱水进行ASTEC验证
核电站乏燃料池(SFP)的冷却失效可能导致燃料组件熔化,并对环境造成严重的放射性后果。为了研究这类事故的第一阶段,直到燃料组件的发现,DENOPI项目是由法国辐射防护和核安全研究所(IRSN1)发起的,由法国政府和合作伙伴支持和资助。在该项目开发的不同设施中,MIDI设施旨在研究大型水池中发生的复杂热工水力现象,该水池由布置在专用机架中的电棒从底部加热。MIDI通过同质缩放到典型的法国SFP。不同的装配安排(加载模式)已经在不同的功率水平下进行了测试,要么是均匀的功率再分配,要么是热电池和冷电池。在每次试验中,跟踪不同海拔高度的水位和温度,以及进入每个燃料架的质量流量。这些实验结果也为小型模块化反应堆浸入式被动排热系统中预期的大自然对流回路的分析和理解提供了相关数据。即将进行的经合发组织/国家环境局POLCA项目旨在扩大这种结果数据库,特别是评估热工力学代码重现这些实验结果的主要趋势的能力。IRSN开发的ASTEC代码是专门用于模拟可能导致放射性物质泄漏的核设施重大事故的系统代码。MUSA欧洲项目最近的工作表明,在事故的第一阶段,在池脱水期间,减少模型不确定性的重要性。本文首先用ASTEC进行了MIDI试验的模拟,以评估和提高ASTEC在失冷事故中模拟SFP等大型水池脱水的能力。对不同加热模式和功率水平的MIDI试验进行了模拟。在ASTEC中测试了文献中不同的过冷沸腾模型,强调了这些模型对准确预测实验流的关键作用。
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来源期刊
Annals of Nuclear Energy
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.
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