Assessing the Phebus FPT-1 experiment: Insights from MELCOR 2.2 and ASYST codes

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology Pub Date : 2024-07-14 DOI:10.1016/j.net.2024.07.021

Peter Mician , Tomas Cerny , Taron Petrosyan , Stepan Foral , Karel Katovsky , Michal Ptacek

引用次数: 0

Abstract

Phebus is an experimental facility that represents a scaled-down version of the French 900 MWe pressurized water reactor (PWR) with a ratio of 1/5000. In order to study phenomena occurring during severe accidents in light water reactors, five experiments (FPT-0 to FPT-4) were performed under different fuel and cooling conditions. This paper provides a comprehensive description of the Phebus FPT-1 experiment, MELCOR and ASYST computer codes, discusses the modelling approaches employed and compares the calculated results with the experimental data. To quantitatively assess the results, the Figure of Merits of selected parameters were calculated for both computer codes using ACAP software.

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评估 Phebus FPT-1 试验：从 MELCOR 2.2 和 ASYST 代码中获得的启示

Phebus 是一个实验设施，是法国 900 兆瓦压水反应堆（PWR）的缩小版，比例为 1/5000。为了研究轻水反应堆发生严重事故时的现象，在不同的燃料和冷却条件下进行了五次实验（FPT-0 至 FPT-4）。本文全面介绍了 Phebus FPT-1 实验、MELCOR 和 ASYST 计算机代码，讨论了所采用的建模方法，并将计算结果与实验数据进行了比较。为了对结果进行定量评估，使用 ACAP 软件计算了两种计算机代码选定参数的优劣图。

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

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

CiteScore

4.80

自引率

7.40%

发文量

431

审稿时长

3.5 months

期刊介绍： Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development