{"title":"自然循环沸水堆启动瞬态预测的TRACE评估","authors":"Yang Zhao, Yunlin Xu, 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, Yunlin Xu, 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}
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.
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.