{"title":"Capabilities of simple calculation models for the analysis of power reactors","authors":"Mohamed A. Gaheen","doi":"10.1016/j.net.2025.103762","DOIUrl":null,"url":null,"abstract":"<div><div>A simple model was developed for the calculation of the coupled kinetics and thermal-hydraulics response of power reactor cores. The developed model was used for the analysis of the Special Power Excursion Reactor Test III (SPERT-III) E-Core and Loss of Fluid Test (LOFT) Experiment L9-3. The model prediction results were compared with the experimental data for the reactivity insertion and loss of secondary feed water transients without scram. The comparison showed that the model predictions are accurate enough to confirm the capabilities and adequacy of the model. It can be concluded that the model results provide confidence in the application of simple calculation models to the analysis of power transients.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103762"},"PeriodicalIF":2.6000,"publicationDate":"2025-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S1738573325003304","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
A simple model was developed for the calculation of the coupled kinetics and thermal-hydraulics response of power reactor cores. The developed model was used for the analysis of the Special Power Excursion Reactor Test III (SPERT-III) E-Core and Loss of Fluid Test (LOFT) Experiment L9-3. The model prediction results were compared with the experimental data for the reactivity insertion and loss of secondary feed water transients without scram. The comparison showed that the model predictions are accurate enough to confirm the capabilities and adequacy of the model. It can be concluded that the model results provide confidence in the application of simple calculation models to the analysis of power transients.
建立了一个简单的动力堆堆芯动力学和热工水力学耦合响应计算模型。所建立的模型用于特殊功率偏移堆试验III (SPERT-III) e -堆芯和流体损失试验(LOFT)实验L9-3的分析。将模型预测结果与实验数据进行了比较,分析了无停堆情况下二次给水瞬态的反应性插入和损失。对比表明,模型预测的准确性足以证实模型的能力和充分性。模型结果为简单计算模型应用于电力暂态分析提供了依据。
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