P. Yarsky , J. Thompson , M. Bernard , J. Valverde
{"title":"NuScale US460螺旋盘管蒸汽发生器密度波振荡的方法学及验证性分析","authors":"P. Yarsky , J. Thompson , M. Bernard , J. Valverde","doi":"10.1016/j.nucengdes.2025.114442","DOIUrl":null,"url":null,"abstract":"<div><div>In the current work, a TRAC-RELAP Advanced Computational Engine (TRACE) model was developed to study density wave oscillations (DWOs) in helical coil steam generator (HCSG) coils of the NuScale US460 design. The NuScale US460 design comprises an integral pressurized water reactor vessel that utilizes natural circulation to provide normal core flow. Heat is removed from the reactor pressure vessel by a pair of intertwined HCSGs. Secondary flow boils and becomes superheated inside the coils of the HCSGs. Under certain conditions, the flow in these coils may become unstable due to the density wave instability mechanism. The regulatory purpose is to evaluate the thermal and hydrodynamic loads of postulated instability to determine if these loads pose a challenge to the integrity of the coils. The Evaluation Model Development and Assessment Process (EMDAP) guided the model development effort. A Phenomena Identification and Ranking Table (PIRT) was used to determine knowledge and assessment gaps relative to key phenomena. Incremental TRACE assessment was performed to support the applicability of TRACE to analyze DWOs in helical coils. The authors considered the possibility of DWOs leading to condensation induced water hammer (CIWH) and developed an approach for conservatively estimating CIWH overpressure loads using TRACE. TRACE calculations were performed over the startup range of the NuScale US460 design where unstable DWOs could occur. TRACE predicted that certain operating conditions during startup would lead to unstable DWOs in the HCSG coils. The most severe instabilities were further evaluated to determine the safety significance. The results show that CIWH is unlikely to occur and that thermal fatigue considerations are manageable.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114442"},"PeriodicalIF":2.1000,"publicationDate":"2025-09-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Methodology and confirmatory analysis for density wave oscillation in NuScale US460 helical coil steam generators\",\"authors\":\"P. Yarsky , J. Thompson , M. Bernard , J. Valverde\",\"doi\":\"10.1016/j.nucengdes.2025.114442\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>In the current work, a TRAC-RELAP Advanced Computational Engine (TRACE) model was developed to study density wave oscillations (DWOs) in helical coil steam generator (HCSG) coils of the NuScale US460 design. The NuScale US460 design comprises an integral pressurized water reactor vessel that utilizes natural circulation to provide normal core flow. Heat is removed from the reactor pressure vessel by a pair of intertwined HCSGs. Secondary flow boils and becomes superheated inside the coils of the HCSGs. Under certain conditions, the flow in these coils may become unstable due to the density wave instability mechanism. The regulatory purpose is to evaluate the thermal and hydrodynamic loads of postulated instability to determine if these loads pose a challenge to the integrity of the coils. The Evaluation Model Development and Assessment Process (EMDAP) guided the model development effort. A Phenomena Identification and Ranking Table (PIRT) was used to determine knowledge and assessment gaps relative to key phenomena. Incremental TRACE assessment was performed to support the applicability of TRACE to analyze DWOs in helical coils. The authors considered the possibility of DWOs leading to condensation induced water hammer (CIWH) and developed an approach for conservatively estimating CIWH overpressure loads using TRACE. TRACE calculations were performed over the startup range of the NuScale US460 design where unstable DWOs could occur. TRACE predicted that certain operating conditions during startup would lead to unstable DWOs in the HCSG coils. The most severe instabilities were further evaluated to determine the safety significance. The results show that CIWH is unlikely to occur and that thermal fatigue considerations are manageable.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"445 \",\"pages\":\"Article 114442\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-09-11\",\"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/S0029549325006193\",\"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/S0029549325006193","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}
Methodology and confirmatory analysis for density wave oscillation in NuScale US460 helical coil steam generators
In the current work, a TRAC-RELAP Advanced Computational Engine (TRACE) model was developed to study density wave oscillations (DWOs) in helical coil steam generator (HCSG) coils of the NuScale US460 design. The NuScale US460 design comprises an integral pressurized water reactor vessel that utilizes natural circulation to provide normal core flow. Heat is removed from the reactor pressure vessel by a pair of intertwined HCSGs. Secondary flow boils and becomes superheated inside the coils of the HCSGs. Under certain conditions, the flow in these coils may become unstable due to the density wave instability mechanism. The regulatory purpose is to evaluate the thermal and hydrodynamic loads of postulated instability to determine if these loads pose a challenge to the integrity of the coils. The Evaluation Model Development and Assessment Process (EMDAP) guided the model development effort. A Phenomena Identification and Ranking Table (PIRT) was used to determine knowledge and assessment gaps relative to key phenomena. Incremental TRACE assessment was performed to support the applicability of TRACE to analyze DWOs in helical coils. The authors considered the possibility of DWOs leading to condensation induced water hammer (CIWH) and developed an approach for conservatively estimating CIWH overpressure loads using TRACE. TRACE calculations were performed over the startup range of the NuScale US460 design where unstable DWOs could occur. TRACE predicted that certain operating conditions during startup would lead to unstable DWOs in the HCSG coils. The most severe instabilities were further evaluated to determine the safety significance. The results show that CIWH is unlikely to occur and that thermal fatigue considerations are manageable.
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.