{"title":"Finding leaking fuel in the core based on 134Cs and 137Cs activities during spiking events","authors":"I.A. Evdokimov , D.V. Dmitriev , A.G. Khromov , E.Y. Afanasieva , P.M. Kalinichev , A.A. Sorokin , I.O. Goryushin , A.Y. Burtsev , S.P. Zolotarev , S.V. Babkin , T.Y. Kvichanskaya , V.V. Atrazhev","doi":"10.1016/j.nucengdes.2025.114439","DOIUrl":null,"url":null,"abstract":"<div><div>At present, the ratio of <sup>134</sup>Cs and <sup>137</sup>Cs activities during spiking events is widely considered to be the best indicator of fuel burnup in leaking fuel rods. Evaluations are performed by comparison of the ratio between <sup>134</sup>Cs and <sup>137</sup>Cs activities in primary coolant with a reference function of fuel burnup. However, there is no universal correlation between the <sup>134</sup>Cs/<sup>137</sup>Cs activity ratio and fuel burnup. Since <sup>134</sup>Cs is produced through neutron capture, the <sup>134</sup>Cs/<sup>137</sup>Cs activity ratio in fuel depends on neutron energy spectrum. The spectrum is sensitive to fuel enrichment and burnup as well as to fission, moderation and absorption characteristics of the surrounding environment. For this reason, the <sup>134</sup>Cs/<sup>137</sup>Cs activity ratio as a function of burnup differs for different fuel types and changes from cycle to cycle every time when the fuel loading pattern in the core is varied. Using a unified correlation in practice introduces significant errors in the evaluation of leaking fuel burnup. A new approach is developed for the identification of leaking FAs in the core. In this approach, <sup>134</sup>Cs and <sup>137</sup>Cs inventory is calculated with low computational costs for each fuel rod in reactor. A software application has been developed to automatically identify fuel rods in the core that provide the closest agreement with the <sup>134</sup>Cs/<sup>137</sup>Cs activity ratio measured during the spiking event. The developed approach was validated on NPP data for 14 fuel cycles, each containing a single leaking FA. None of the 14 leaking FAs matched the burnup range predicted by the standard technique, with difference ranging from ∼ 10 to 35<!--> <!-->MWd/kgU. In contrast, the new approach accurately identified all 14 leaking FAs and prioritized them for leakage testing during reactor outage.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114439"},"PeriodicalIF":2.1000,"publicationDate":"2025-09-09","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/S0029549325006168","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
Abstract
At present, the ratio of 134Cs and 137Cs activities during spiking events is widely considered to be the best indicator of fuel burnup in leaking fuel rods. Evaluations are performed by comparison of the ratio between 134Cs and 137Cs activities in primary coolant with a reference function of fuel burnup. However, there is no universal correlation between the 134Cs/137Cs activity ratio and fuel burnup. Since 134Cs is produced through neutron capture, the 134Cs/137Cs activity ratio in fuel depends on neutron energy spectrum. The spectrum is sensitive to fuel enrichment and burnup as well as to fission, moderation and absorption characteristics of the surrounding environment. For this reason, the 134Cs/137Cs activity ratio as a function of burnup differs for different fuel types and changes from cycle to cycle every time when the fuel loading pattern in the core is varied. Using a unified correlation in practice introduces significant errors in the evaluation of leaking fuel burnup. A new approach is developed for the identification of leaking FAs in the core. In this approach, 134Cs and 137Cs inventory is calculated with low computational costs for each fuel rod in reactor. A software application has been developed to automatically identify fuel rods in the core that provide the closest agreement with the 134Cs/137Cs activity ratio measured during the spiking event. The developed approach was validated on NPP data for 14 fuel cycles, each containing a single leaking FA. None of the 14 leaking FAs matched the burnup range predicted by the standard technique, with difference ranging from ∼ 10 to 35 MWd/kgU. In contrast, the new approach accurately identified all 14 leaking FAs and prioritized them for leakage testing during reactor outage.
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.