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

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
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 ,&nbsp;Gyanender Singh ,&nbsp;Kyle Gamble ,&nbsp;David Kamerman ,&nbsp;Seokbin Seo ,&nbsp;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 ,&nbsp;Gyanender Singh ,&nbsp;Kyle Gamble ,&nbsp;David Kamerman ,&nbsp;Seokbin Seo ,&nbsp;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}
引用次数: 0

摘要

容错性燃料(atf)旨在增加事故发生后的应对时间,同时保持或改善反应堆当前的稳态运行性能。一种潜在的ATF概念是使用碳化硅(SiC)-SiC复合包层。在基于sic - sic的包层概念上进行了燃料性能模拟,利用多层方法来提高性能。这种包层概念在本文中被称为“双相概念”,因为它是由放置在内部SiC-SiC复合层外面的单片SiC层组成的双相结构。单片SiC层用于为棒提供气密性,并保护SiC-SiC复合层不暴露于冷却剂。在燃料包壳间隙中加入液态金属,以改善燃料和包壳之间的热传递。在这项工作中,使用BISON燃料性能代码对包层概念进行燃料性能模拟。在四种相关条件下,与目前由二氧化铀(UO2)燃料包裹在锆-4包层中的原型燃料棒设计进行了比较。对于条件I(正常操作),考虑了两种具有代表性的稳态情况,一种具有恒定的棒平均热率,另一种具有初始较高的热率。对于条件II事件,模拟了一个颗粒包层相互作用(PCI)斜坡情况,以分析潜在的预期操作事件。还模拟了冷却剂损失事故(LOCA)和反应性引发事故(RIA)期间的条件III/IV瞬态响应。该计算研究表明,在正常工作条件下,SiC概念包层的性能与评估的标准功率情况下的基线一样好。斜坡评价表明,由于温度梯度和随后在复合材料厚度上的导热系数退化和膨胀差异,与锆合金-4包层相比,SiC-SiC复合包层可能更早破裂。在条件III/IV事件中,SiC-SiC双相概念在700 J/g RIA后保持完整,类似于Zircaloy-4燃料系统。在LOCA条件下,双相概念的性能得到了显著改善,与Zircaloy-4相比,它保持完好无损。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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.
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