John Alvis , Gyanender Singh , Kyle Gamble , David Kamerman , Seokbin Seo , Katheren Nantes
{"title":"轻水反应堆环境中sic - sic复合包覆燃料销概念的热力学评估","authors":"John Alvis , Gyanender Singh , Kyle Gamble , David Kamerman , Seokbin Seo , Katheren Nantes","doi":"10.1016/j.nucengdes.2025.114458","DOIUrl":null,"url":null,"abstract":"<div><div>Accident-tolerant fuels (ATFs) are designed to increase coping time following an accident scenario while preserving or improving current steady-state reactor operational performance. A potential ATF concept is using silicon carbide (SiC)-SiC-composite claddings. Fuel-performance simulations were conducted on a SiC-SiC-based cladding concept utilizing a multilayered approach for improved performance. This cladding concept is referred to in this paper as “the duplex concept” as it is a duplex structure composed of a monolithic SiC layer placed on the outside of an inner SiC-SiC composite layer. The monolithic SiC layer is used to provide gas tightness to the rod and protect the SiC-SiC-composite layer from exposure to the coolant. A liquid metal is added to the fuel-cladding gap for improved thermal transport between the fuel and the cladding. In this work, the BISON fuel-performance code was used to conduct fuel-performance simulations on the cladding concept. Comparisons are made with a current prototypic fuel-rod design consisting of uranium dioxide (UO<sub>2</sub>) fuel enclosed in Zircaloy-4 cladding under four relevant conditions. For condition I (normal operations) two representative steady-state cases were considered, one with a constant rod average heat rate, and one with an initially higher heat rate. For condition II events, a pellet-cladding interaction (PCI) ramp case was simulated to analyze potential anticipated operational occurrences. Condition III/IV transient responses during a loss of coolant accident (LOCA) and a reactivity-initiated accident (RIA) were also simulated. This computational study demonstrated that for normal operating conditions, the SiC concept cladding performed as well as the baseline for the standard-power cases evaluated. The ramping evaluations indicate potential for earlier fracturing of the SiC-SiC composite cladding compared to the Zircaloy-4 cladding due to the temperature gradient and the subsequent differential thermal conductivity degradation and swelling across the composite thickness. In condition III/IV events the SiC-SiC duplex concept remains intact after a 700 J/g RIA similar to Zircaloy-4 fuel systems. Under LOCA conditions, the duplex concept showed significantly improved performance, remaining intact in contrast to Zircaloy-4 which ballons and bursts.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114458"},"PeriodicalIF":2.1000,"publicationDate":"2025-09-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Thermal mechanical assessment of a SiC-SiC-composite clad fuel pin concept in a light water reactor environment\",\"authors\":\"John Alvis , Gyanender Singh , Kyle Gamble , David Kamerman , Seokbin Seo , Katheren Nantes\",\"doi\":\"10.1016/j.nucengdes.2025.114458\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Accident-tolerant fuels (ATFs) are designed to increase coping time following an accident scenario while preserving or improving current steady-state reactor operational performance. A potential ATF concept is using silicon carbide (SiC)-SiC-composite claddings. Fuel-performance simulations were conducted on a SiC-SiC-based cladding concept utilizing a multilayered approach for improved performance. This cladding concept is referred to in this paper as “the duplex concept” as it is a duplex structure composed of a monolithic SiC layer placed on the outside of an inner SiC-SiC composite layer. The monolithic SiC layer is used to provide gas tightness to the rod and protect the SiC-SiC-composite layer from exposure to the coolant. A liquid metal is added to the fuel-cladding gap for improved thermal transport between the fuel and the cladding. In this work, the BISON fuel-performance code was used to conduct fuel-performance simulations on the cladding concept. Comparisons are made with a current prototypic fuel-rod design consisting of uranium dioxide (UO<sub>2</sub>) fuel enclosed in Zircaloy-4 cladding under four relevant conditions. For condition I (normal operations) two representative steady-state cases were considered, one with a constant rod average heat rate, and one with an initially higher heat rate. For condition II events, a pellet-cladding interaction (PCI) ramp case was simulated to analyze potential anticipated operational occurrences. Condition III/IV transient responses during a loss of coolant accident (LOCA) and a reactivity-initiated accident (RIA) were also simulated. This computational study demonstrated that for normal operating conditions, the SiC concept cladding performed as well as the baseline for the standard-power cases evaluated. The ramping evaluations indicate potential for earlier fracturing of the SiC-SiC composite cladding compared to the Zircaloy-4 cladding due to the temperature gradient and the subsequent differential thermal conductivity degradation and swelling across the composite thickness. In condition III/IV events the SiC-SiC duplex concept remains intact after a 700 J/g RIA similar to Zircaloy-4 fuel systems. Under LOCA conditions, the duplex concept showed significantly improved performance, remaining intact in contrast to Zircaloy-4 which ballons and bursts.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"445 \",\"pages\":\"Article 114458\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-09-24\",\"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/S0029549325006351\",\"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/S0029549325006351","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}
Thermal mechanical assessment of a SiC-SiC-composite clad fuel pin concept in a light water reactor environment
Accident-tolerant fuels (ATFs) are designed to increase coping time following an accident scenario while preserving or improving current steady-state reactor operational performance. A potential ATF concept is using silicon carbide (SiC)-SiC-composite claddings. Fuel-performance simulations were conducted on a SiC-SiC-based cladding concept utilizing a multilayered approach for improved performance. This cladding concept is referred to in this paper as “the duplex concept” as it is a duplex structure composed of a monolithic SiC layer placed on the outside of an inner SiC-SiC composite layer. The monolithic SiC layer is used to provide gas tightness to the rod and protect the SiC-SiC-composite layer from exposure to the coolant. A liquid metal is added to the fuel-cladding gap for improved thermal transport between the fuel and the cladding. In this work, the BISON fuel-performance code was used to conduct fuel-performance simulations on the cladding concept. Comparisons are made with a current prototypic fuel-rod design consisting of uranium dioxide (UO2) fuel enclosed in Zircaloy-4 cladding under four relevant conditions. For condition I (normal operations) two representative steady-state cases were considered, one with a constant rod average heat rate, and one with an initially higher heat rate. For condition II events, a pellet-cladding interaction (PCI) ramp case was simulated to analyze potential anticipated operational occurrences. Condition III/IV transient responses during a loss of coolant accident (LOCA) and a reactivity-initiated accident (RIA) were also simulated. This computational study demonstrated that for normal operating conditions, the SiC concept cladding performed as well as the baseline for the standard-power cases evaluated. The ramping evaluations indicate potential for earlier fracturing of the SiC-SiC composite cladding compared to the Zircaloy-4 cladding due to the temperature gradient and the subsequent differential thermal conductivity degradation and swelling across the composite thickness. In condition III/IV events the SiC-SiC duplex concept remains intact after a 700 J/g RIA similar to Zircaloy-4 fuel systems. Under LOCA conditions, the duplex concept showed significantly improved performance, remaining intact in contrast to Zircaloy-4 which ballons and bursts.
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.