自然循环沸水堆启动瞬态预测的TRACE评估

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yang Zhao, Yunlin Xu, Mamoru Ishii
{"title":"自然循环沸水堆启动瞬态预测的TRACE评估","authors":"Yang Zhao,&nbsp;Yunlin Xu,&nbsp;Mamoru Ishii","doi":"10.1016/j.nucengdes.2025.114430","DOIUrl":null,"url":null,"abstract":"<div><div>Natural circulation is a key passive safety feature in several light water small modular reactor (SMR) designs, but flow instabilities during natural circulation startup transients pose critical challenges for safety analysis. To ensure accurate prediction of key thermal–hydraulic phenomena in startup transients, system-level analysis codes must be rigorously assessed. Among these, TRACE is recognized as the flagship best-estimate reactor system code developed by the U.S. Nuclear Regulatory Commission (NRC). This study evaluates TRACE (V5p8) for predicting two-phase flow behavior in natural circulation using startup transient data from the Purdue University Multidimensional Integral Test Assembly (PUMA). Four startup tests (EQU, EQU-NU, SUP, SUP-NU) were analyzed, simulating natural circulation boiling water reactor (BWR) behavior under different pressure conditions, both with and without neutronic feedback. A systematic refinement study was conducted to determine the optimal TRACE simulation settings, including nodalization, timesteps, and spatial discretization methods. Results indicate that TRACE successfully handles input power oscillations without significant numerical instabilities and generally provides reasonable predictions. While TRACE accurately predicts system pressure and liquid temperature, it significantly underestimates core void fractions, failing to capture geysering phenomena due to underprediction of energy allocated for void generation in subcooled boiling flow. The flashing phenomenon in the chimney is well captured, but chimney void fractions are generally overestimated. Additionally, TRACE overestimates downcomer flow rates in most cases, potentially due to the overestimation of chimney void fraction, which influences natural circulation gravity head. Future work will focus on further validation of TRACE models using an extended natural circulation database from separate effect tests (SETs) and integral effect tests (IETs) to enhance modeling accuracy for complex startup transients in natural circulation systems.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"444 ","pages":"Article 114430"},"PeriodicalIF":2.1000,"publicationDate":"2025-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Assessment of TRACE for predicting startup transients in natural circulation boiling water reactors\",\"authors\":\"Yang Zhao,&nbsp;Yunlin Xu,&nbsp;Mamoru Ishii\",\"doi\":\"10.1016/j.nucengdes.2025.114430\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Natural circulation is a key passive safety feature in several light water small modular reactor (SMR) designs, but flow instabilities during natural circulation startup transients pose critical challenges for safety analysis. To ensure accurate prediction of key thermal–hydraulic phenomena in startup transients, system-level analysis codes must be rigorously assessed. Among these, TRACE is recognized as the flagship best-estimate reactor system code developed by the U.S. Nuclear Regulatory Commission (NRC). This study evaluates TRACE (V5p8) for predicting two-phase flow behavior in natural circulation using startup transient data from the Purdue University Multidimensional Integral Test Assembly (PUMA). Four startup tests (EQU, EQU-NU, SUP, SUP-NU) were analyzed, simulating natural circulation boiling water reactor (BWR) behavior under different pressure conditions, both with and without neutronic feedback. A systematic refinement study was conducted to determine the optimal TRACE simulation settings, including nodalization, timesteps, and spatial discretization methods. Results indicate that TRACE successfully handles input power oscillations without significant numerical instabilities and generally provides reasonable predictions. While TRACE accurately predicts system pressure and liquid temperature, it significantly underestimates core void fractions, failing to capture geysering phenomena due to underprediction of energy allocated for void generation in subcooled boiling flow. The flashing phenomenon in the chimney is well captured, but chimney void fractions are generally overestimated. Additionally, TRACE overestimates downcomer flow rates in most cases, potentially due to the overestimation of chimney void fraction, which influences natural circulation gravity head. Future work will focus on further validation of TRACE models using an extended natural circulation database from separate effect tests (SETs) and integral effect tests (IETs) to enhance modeling accuracy for complex startup transients in natural circulation systems.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"444 \",\"pages\":\"Article 114430\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-08-30\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0029549325006077\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325006077","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

摘要

自然循环是一些轻水小型模块化反应堆(SMR)设计中关键的被动安全特性,但自然循环启动瞬态的流动不稳定性给安全性分析带来了重大挑战。为了准确预测启动瞬态的关键热液现象,必须对系统级分析代码进行严格的评估。其中,TRACE被公认为美国核管理委员会(NRC)开发的最佳评估反应堆系统代码的旗舰。本研究利用普渡大学多维积分测试组件(PUMA)的启动瞬态数据,评估了TRACE (V5p8)在自然循环中预测两相流动行为的能力。分析了四种启动试验(EQU、equu - nu、SUP、SUP- nu),模拟了自然循环沸水堆(BWR)在有和无中子反馈的不同压力条件下的运行行为。进行了系统的细化研究,以确定最佳的TRACE模拟设置,包括节点化,时间步长和空间离散化方法。结果表明,TRACE成功地处理了输入功率振荡,没有明显的数值不稳定性,并且总体上提供了合理的预测。虽然TRACE能准确预测系统压力和液体温度,但它明显低估了岩心空隙分数,由于低估了在过冷沸腾流动中分配给空隙生成的能量,无法捕捉间歇泉现象。烟囱内的闪烁现象被很好地捕捉到了,但烟囱空洞分数通常被高估了。此外,TRACE在大多数情况下高估了降水管流量,这可能是由于高估了烟囱空隙率,这会影响自然循环重力水头。未来的工作将侧重于使用扩展的自然循环数据库,从分离效应测试(SETs)和积分效应测试(IETs)中进一步验证TRACE模型,以提高自然循环系统中复杂启动瞬态的建模精度。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Assessment of TRACE for predicting startup transients in natural circulation boiling water reactors
Natural circulation is a key passive safety feature in several light water small modular reactor (SMR) designs, but flow instabilities during natural circulation startup transients pose critical challenges for safety analysis. To ensure accurate prediction of key thermal–hydraulic phenomena in startup transients, system-level analysis codes must be rigorously assessed. Among these, TRACE is recognized as the flagship best-estimate reactor system code developed by the U.S. Nuclear Regulatory Commission (NRC). This study evaluates TRACE (V5p8) for predicting two-phase flow behavior in natural circulation using startup transient data from the Purdue University Multidimensional Integral Test Assembly (PUMA). Four startup tests (EQU, EQU-NU, SUP, SUP-NU) were analyzed, simulating natural circulation boiling water reactor (BWR) behavior under different pressure conditions, both with and without neutronic feedback. A systematic refinement study was conducted to determine the optimal TRACE simulation settings, including nodalization, timesteps, and spatial discretization methods. Results indicate that TRACE successfully handles input power oscillations without significant numerical instabilities and generally provides reasonable predictions. While TRACE accurately predicts system pressure and liquid temperature, it significantly underestimates core void fractions, failing to capture geysering phenomena due to underprediction of energy allocated for void generation in subcooled boiling flow. The flashing phenomenon in the chimney is well captured, but chimney void fractions are generally overestimated. Additionally, TRACE overestimates downcomer flow rates in most cases, potentially due to the overestimation of chimney void fraction, which influences natural circulation gravity head. Future work will focus on further validation of TRACE models using an extended natural circulation database from separate effect tests (SETs) and integral effect tests (IETs) to enhance modeling accuracy for complex startup transients in natural circulation systems.
求助全文
通过发布文献求助,成功后即可免费获取论文全文。 去求助
来源期刊
Nuclear Engineering and Design
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.
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:604180095
Book学术官方微信