对ELSMOR被动排热系统进行的试验进行了CATHARE计算

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-09-01 DOI:10.1016/j.nucengdes.2025.114437

B. Grosjean , R. Ferri , C. Lombardo

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引用次数: 0

摘要

作为ELSMOR（向欧洲许可小型模块化反应堆）项目的一部分，在SIET（意大利皮亚琴察）建立了一个实验设施来测试被动散热系统。这种无源系统在自然循环中运行，有三个不同的回路：一次回路（PC，热源），二次回路（SC，自压）和第三回路（散热器，由池表示）。一次回路和二次回路与板式紧凑型蒸汽发生器（CSG）热耦合，而二次回路和三次回路与池内冷凝器耦合。通过不同类型的测试（如二次侧充注比（FR）或不凝性气体（NC）浓度、一次系统温度、池液位等），开展了一项实验活动，以研究不同参数对被动系统行为的影响。采用CATHARE 3（法国系统计算代码）对试验进行了建模，并将计算结果与实验数据进行了比较。CATHARE 3规范对设备主要参数（交换功率、二次回路压力、冷凝器出口温度）的测试预测良好。对于大多数测试，CSG中交换功率的实验结果与计算结果之间的差异在10%以下：对于SC中高FR， CATHARE 3代码可以很好地预测交换功率，而对于低FR，则高估了功率。灵敏度计算表明，凝汽器对设施性能有主要影响（CSG的影响有限）；其中，二次侧相关系数对交换功率的影响显著，而三次侧相关系数的影响较小；因此，三级模拟对计算结果的影响较小。对于所有测试，CATHARE 3代码都低估了中美合作所出口温度，高估了超临界流体中的压力。尽管如此，实验不确定性的存在，特别是与未表征的水头损失和两相流条件相关的不确定性，阻碍了对模型准确性做出完全结论性的陈述。

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CATHARE calculation of the tests conducted on the ELSMOR passive heat removal system

As part of the ELSMOR (Toward European Licensing of Small Modular Reactors) project, an experimental facility has been set up at SIET (Piacenza, Italy) to test a passive heat removal system. Such a passive system operates in natural circulation, with three different circuits: a primary circuit (PC, the heat source), a secondary circuit (SC, self-pressurised) and a tertiary circuit (the heat sink, represented by a pool). The primary and the secondary circuits are thermally coupled to a plate-type Compact Steam Generator (CSG), while the secondary and the tertiary circuits are coupled to an in-pool condenser. An experimental campaign has been carried out to investigate the effect of different parameters on the passive system behavior, through different types of tests (e.g. secondary side filling ratio (FR) or non-condensable gas (NC) concentration, primary system temperature, pool level, etc.). These experimental tests are modelled with the CATHARE 3 code (French system calculation code) and the calculation results are compared with the experimental data. The CATHARE 3 code predicts good tendencies for the tests on the main parameters of the facility (exchanged power, secondary circuit pressure, condenser outlet temperature). For the majority of the tests, the discrepancy between experimental and calculation results for the exchanged power in the CSG is below 10 %: for high FR in the SC, the CATHARE 3 code predicts the exchanged power well, while for low FR the power is overestimated. Sensitivity calculations showed that the condenser has the main influence on the facility behavior (the CSG has a limited influence); in particular, the correlations in the secondary side of the condenser have a significant influence on the exchanged power, while the correlations in the tertiary side have a small influence; thus, the tertiary modelling has a small influence on the calculation results. For all tests, the CATHARE 3 code underestimates the SACO outlet temperature and overestimates the pressure in the SC. Nonetheless, the presence of experimental uncertainties, particularly related to uncharacterized head losses and two-phase flow conditions, prevents drawing fully conclusive statements about the model accuracy.

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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.