Assessment of RELAP5/SCDAPSIM code against NACIE-UP facility tests

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2025-04-05 DOI:10.1016/j.pnucene.2025.105775

Daniel Dupleac, Roxana-Mihaela Nistor-Vlad

{"title":"Assessment of RELAP5/SCDAPSIM code against NACIE-UP facility tests","authors":"Daniel Dupleac, Roxana-Mihaela Nistor-Vlad","doi":"10.1016/j.pnucene.2025.105775","DOIUrl":null,"url":null,"abstract":"<div><div>During the 2017 campaign, ADP10 and ADP06 tests were performed in NAtural Circulation Experiment – Upgraded (NACIE-UP) facility built at ENEA Brasimone Research Centre to analyze the behavior of the 19-pins wire-spaced fuel pin bundle simulator (FPS) during the transition from forced to natural circulation flow. Although the total heating power is the same in both tests, in the ADP10 test the power was uniformly distributed among the 19 electrically heated pins, whereas in the ADP06 test, only the 7 central pins were switched-on. The present paper presents the application of RELAP5/SCDAPSIM/MOD4.1 (RS4.1) code for ADP10 and ADP06 tests subchannel analysis. RELAP/SCDAPSIM code is a system code initially designed for the thermal-hydraulic and safety analysis of Light Water Reactors (LWRs). Over the years, the code has been extensively improved by incorporating additional fluid properties used as coolants for advanced reactors, among which molten lead, lead-bismuth eutectic (LBE) and molten salts. Although the RS4.1 is a system code the present paper describes the code capabilities in predicting the subchannels thermal behavior under the ADP10 and ADP06 test conditions from the NACIE-UP facility. RS4.1 simulations results for LBE mass flow rate and temperature measured by thermocouples showed good agreement with experimental data which indicates that RS4.1 code can be successfully employed as subchannel code.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"185 ","pages":"Article 105775"},"PeriodicalIF":3.3000,"publicationDate":"2025-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197025001738","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

During the 2017 campaign, ADP10 and ADP06 tests were performed in NAtural Circulation Experiment – Upgraded (NACIE-UP) facility built at ENEA Brasimone Research Centre to analyze the behavior of the 19-pins wire-spaced fuel pin bundle simulator (FPS) during the transition from forced to natural circulation flow. Although the total heating power is the same in both tests, in the ADP10 test the power was uniformly distributed among the 19 electrically heated pins, whereas in the ADP06 test, only the 7 central pins were switched-on. The present paper presents the application of RELAP5/SCDAPSIM/MOD4.1 (RS4.1) code for ADP10 and ADP06 tests subchannel analysis. RELAP/SCDAPSIM code is a system code initially designed for the thermal-hydraulic and safety analysis of Light Water Reactors (LWRs). Over the years, the code has been extensively improved by incorporating additional fluid properties used as coolants for advanced reactors, among which molten lead, lead-bismuth eutectic (LBE) and molten salts. Although the RS4.1 is a system code the present paper describes the code capabilities in predicting the subchannels thermal behavior under the ADP10 and ADP06 test conditions from the NACIE-UP facility. RS4.1 simulations results for LBE mass flow rate and temperature measured by thermocouples showed good agreement with experimental data which indicates that RS4.1 code can be successfully employed as subchannel code.

查看原文本刊更多论文

求助全文

约1分钟内获得全文求助全文

来源期刊

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.