高温气冷堆燃耗标定及其与辐照历史的关系

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-04-30 DOI:10.1016/j.nucengdes.2025.114078

Hongjian Zhang, Liguo Zhang, Yu Wang, Yanlong Wen, Qing Zhu, Tao Ma

{"title":"高温气冷堆燃耗标定及其与辐照历史的关系","authors":"Hongjian Zhang, Liguo Zhang, Yu Wang, Yanlong Wen, Qing Zhu, Tao Ma","doi":"10.1016/j.nucengdes.2025.114078","DOIUrl":null,"url":null,"abstract":"<div><div>Accurate online burnup measurement in pebble-bed high-temperature gas-cooled reactors (HTGRs) is a critical technical prerequisite for continuous refueling. This study provided a theoretical analysis of the online burnup measurement methodology for the HTR-PM (High-Temperature Gas-Cooled Reactor Pebble-Bed Module), focusing on the calibration between burnup and Cs-137 activity. Specifically: (1) A general burnup calibration is derived that correlates burnup with Cs-137 activity, accounting for contributions from multiple fissile isotopes. The approximated burnup obtained using this burnup calibration exhibit negligible deviations from the theoretical values. (2) Potential sources of error, such as differences in the fission energy and fission yields of various fissile isotopes, are analyzed.</div><div>To evaluate the applicability of the general burnup calibration and quantify the effects of irradiation history, a multi-cycle frequently-varying irradiation history model was developed. Leveraging KORIGEN and Nuclear Inventory Tool (NUIT) as computational tools, extensive burnup data were generated to establish a fitted burnup calibration. The study then: (1) Compared the general burnup calibration with the fitted burnup calibration. (2) Quantified the impact of frequently-varying irradiation history on burnup calibration accuracy.</div><div>Burnup can be conveniently estimated using a linear correlation with Cs-137 activity. This study builds upon that foundation by introducing theoretical and computational refinements, improved accuracy under long irradiation periods. The results reveal that the relative error between the NUIT-fitted burnup calibration and the general burnup calibration is less than 0.55 %. Additionally, the effect of irradiation history variations on burnup calibration is so small that under identical fuel burnup conditions, the standard deviation of Cs-137 activity is less than 4.0 × 10<sup>8</sup> Bq, with a coefficient of relative variation not exceeding 0.60 %. These findings provided valuable insights for accurately predicting fuel sphere burnup behavior, optimizing fuel management strategies, and ensuring the safe and efficient operation of HTGRs.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"439 ","pages":"Article 114078"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Burnup calibration and its dependence on irradiation history in high-temperature gas-cooled reactors\",\"authors\":\"Hongjian Zhang, Liguo Zhang, Yu Wang, Yanlong Wen, Qing Zhu, Tao Ma\",\"doi\":\"10.1016/j.nucengdes.2025.114078\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Accurate online burnup measurement in pebble-bed high-temperature gas-cooled reactors (HTGRs) is a critical technical prerequisite for continuous refueling. This study provided a theoretical analysis of the online burnup measurement methodology for the HTR-PM (High-Temperature Gas-Cooled Reactor Pebble-Bed Module), focusing on the calibration between burnup and Cs-137 activity. Specifically: (1) A general burnup calibration is derived that correlates burnup with Cs-137 activity, accounting for contributions from multiple fissile isotopes. The approximated burnup obtained using this burnup calibration exhibit negligible deviations from the theoretical values. (2) Potential sources of error, such as differences in the fission energy and fission yields of various fissile isotopes, are analyzed.</div><div>To evaluate the applicability of the general burnup calibration and quantify the effects of irradiation history, a multi-cycle frequently-varying irradiation history model was developed. Leveraging KORIGEN and Nuclear Inventory Tool (NUIT) as computational tools, extensive burnup data were generated to establish a fitted burnup calibration. The study then: (1) Compared the general burnup calibration with the fitted burnup calibration. (2) Quantified the impact of frequently-varying irradiation history on burnup calibration accuracy.</div><div>Burnup can be conveniently estimated using a linear correlation with Cs-137 activity. This study builds upon that foundation by introducing theoretical and computational refinements, improved accuracy under long irradiation periods. The results reveal that the relative error between the NUIT-fitted burnup calibration and the general burnup calibration is less than 0.55 %. Additionally, the effect of irradiation history variations on burnup calibration is so small that under identical fuel burnup conditions, the standard deviation of Cs-137 activity is less than 4.0 × 10<sup>8</sup> Bq, with a coefficient of relative variation not exceeding 0.60 %. These findings provided valuable insights for accurately predicting fuel sphere burnup behavior, optimizing fuel management strategies, and ensuring the safe and efficient operation of HTGRs.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"439 \",\"pages\":\"Article 114078\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-04-30\",\"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/S0029549325002559\",\"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/S0029549325002559","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

球床高温气冷堆（htgr）燃耗在线准确测量是实现连续换料的关键技术前提。本研究对高温气冷堆球床模块（HTR-PM）的在线燃耗测量方法进行了理论分析，重点研究了燃耗与Cs-137活性之间的校准。具体来说：(1)推导出了一个将燃耗与Cs-137活性联系起来的通用燃耗校准，考虑了多种裂变同位素的贡献。使用此燃耗校准获得的近似燃耗与理论值的偏差可以忽略不计。(2)分析了各种可裂变同位素的裂变能和裂变产额的差异等潜在误差来源。为了评估一般燃耗校准的适用性，量化辐照历史的影响，建立了一个多周期频繁变化的辐照历史模型。利用KORIGEN和核库存工具（NUIT）作为计算工具，生成大量燃耗数据，以建立拟合的燃耗校准。然后进行了研究：(1)将一般燃耗校准与拟合燃耗校准进行了比较。(2)量化了频繁变化的辐照历史对燃耗校准精度的影响。燃耗可以用与铯-137活度的线性相关来方便地估计。本研究建立在此基础上，通过引入理论和计算的改进，提高了长辐照周期下的精度。结果表明，该方法与常规燃耗校正方法的相对误差小于0.55%。辐照历史变化对燃耗校准的影响很小，在相同燃料燃耗条件下，Cs-137活度的标准偏差小于4.0 × 108 Bq，相对变异系数不超过0.60%。这些研究结果为准确预测燃料球燃耗行为、优化燃料管理策略以及确保htgr安全高效运行提供了有价值的见解。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

查看原文本刊更多论文

Burnup calibration and its dependence on irradiation history in high-temperature gas-cooled reactors

Accurate online burnup measurement in pebble-bed high-temperature gas-cooled reactors (HTGRs) is a critical technical prerequisite for continuous refueling. This study provided a theoretical analysis of the online burnup measurement methodology for the HTR-PM (High-Temperature Gas-Cooled Reactor Pebble-Bed Module), focusing on the calibration between burnup and Cs-137 activity. Specifically: (1) A general burnup calibration is derived that correlates burnup with Cs-137 activity, accounting for contributions from multiple fissile isotopes. The approximated burnup obtained using this burnup calibration exhibit negligible deviations from the theoretical values. (2) Potential sources of error, such as differences in the fission energy and fission yields of various fissile isotopes, are analyzed.

To evaluate the applicability of the general burnup calibration and quantify the effects of irradiation history, a multi-cycle frequently-varying irradiation history model was developed. Leveraging KORIGEN and Nuclear Inventory Tool (NUIT) as computational tools, extensive burnup data were generated to establish a fitted burnup calibration. The study then: (1) Compared the general burnup calibration with the fitted burnup calibration. (2) Quantified the impact of frequently-varying irradiation history on burnup calibration accuracy.

Burnup can be conveniently estimated using a linear correlation with Cs-137 activity. This study builds upon that foundation by introducing theoretical and computational refinements, improved accuracy under long irradiation periods. The results reveal that the relative error between the NUIT-fitted burnup calibration and the general burnup calibration is less than 0.55 %. Additionally, the effect of irradiation history variations on burnup calibration is so small that under identical fuel burnup conditions, the standard deviation of Cs-137 activity is less than 4.0 × 10⁸ Bq, with a coefficient of relative variation not exceeding 0.60 %. These findings provided valuable insights for accurately predicting fuel sphere burnup behavior, optimizing fuel management strategies, and ensuring the safe and efficient operation of HTGRs.

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 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.