Abidur Rahman Ishraq , Anton Evgenievich Kruglikov , H. Rainad Khan Rohan
{"title":"通过在小型模块化反应堆中实施重新装料-重新洗牌组合计划进行战略性燃料管理","authors":"Abidur Rahman Ishraq , Anton Evgenievich Kruglikov , H. Rainad Khan Rohan","doi":"10.1016/j.nucengdes.2024.113605","DOIUrl":null,"url":null,"abstract":"<div><div>This study aims to implement a coupled fuel reload-reshuffle scheme for a PWR-based SMR. Considering 540 EFPD as the cycle length, a heterogenous poison-free core based on the design of ACP-100 with 57 fuel assemblies (FAs) utilizing three different enrichments (3.0 wt.%, 4.0 wt.%, and 4.45 wt.%) was modeled in SERPENT. Initially, the core achieved a k<sub>eff</sub> of 1.31492 and a radial PPF of 1.77, which decreased to 1.10914 and 1.19 respectively at the end of the first cycle. Reloading 12 fresh FAs and shuffling 32 irradiated FAs within the core at this point increased the k<sub>eff</sub> to 1.1584, sustaining criticality for an additional 540 EFPDs (the second cycle). Two more burnup cycles were simulated with the refueling patterns being established by evaluating the assembly discharge burnup and core power profile. Through a hybrid combination of in-out and out-in loading approaches, a high cumulative average discharge burnup exceeding 30 MWD/kg (over 40 MWD/kg for some assemblies) was achieved at the end of the fourth cycle (2160 EFPDs). Although the employed refueling patterns raised the power peaking factors (PPFs) at the beginning of each cycle, the core power distribution in general became more uniform and the PPF decreased as burnup progressed. Other than the beginning of the fourth cycle, the obtained PPF values were less than or around 2.00 even without the use of any control systems. Both the fuel and moderator temperature coefficients remained sufficiently negative throughout the burnup cycles. Further iterations of the implemented refueling schemes can be carried out depending on plant operational requirements.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"429 ","pages":"Article 113605"},"PeriodicalIF":1.9000,"publicationDate":"2024-09-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Strategic fuel management via implementation of a combined reload-reshuffle scheme in small modular reactors\",\"authors\":\"Abidur Rahman Ishraq , Anton Evgenievich Kruglikov , H. Rainad Khan Rohan\",\"doi\":\"10.1016/j.nucengdes.2024.113605\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>This study aims to implement a coupled fuel reload-reshuffle scheme for a PWR-based SMR. Considering 540 EFPD as the cycle length, a heterogenous poison-free core based on the design of ACP-100 with 57 fuel assemblies (FAs) utilizing three different enrichments (3.0 wt.%, 4.0 wt.%, and 4.45 wt.%) was modeled in SERPENT. Initially, the core achieved a k<sub>eff</sub> of 1.31492 and a radial PPF of 1.77, which decreased to 1.10914 and 1.19 respectively at the end of the first cycle. Reloading 12 fresh FAs and shuffling 32 irradiated FAs within the core at this point increased the k<sub>eff</sub> to 1.1584, sustaining criticality for an additional 540 EFPDs (the second cycle). Two more burnup cycles were simulated with the refueling patterns being established by evaluating the assembly discharge burnup and core power profile. Through a hybrid combination of in-out and out-in loading approaches, a high cumulative average discharge burnup exceeding 30 MWD/kg (over 40 MWD/kg for some assemblies) was achieved at the end of the fourth cycle (2160 EFPDs). Although the employed refueling patterns raised the power peaking factors (PPFs) at the beginning of each cycle, the core power distribution in general became more uniform and the PPF decreased as burnup progressed. Other than the beginning of the fourth cycle, the obtained PPF values were less than or around 2.00 even without the use of any control systems. Both the fuel and moderator temperature coefficients remained sufficiently negative throughout the burnup cycles. Further iterations of the implemented refueling schemes can be carried out depending on plant operational requirements.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"429 \",\"pages\":\"Article 113605\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-09-25\",\"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/S0029549324007052\",\"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/S0029549324007052","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}
Strategic fuel management via implementation of a combined reload-reshuffle scheme in small modular reactors
This study aims to implement a coupled fuel reload-reshuffle scheme for a PWR-based SMR. Considering 540 EFPD as the cycle length, a heterogenous poison-free core based on the design of ACP-100 with 57 fuel assemblies (FAs) utilizing three different enrichments (3.0 wt.%, 4.0 wt.%, and 4.45 wt.%) was modeled in SERPENT. Initially, the core achieved a keff of 1.31492 and a radial PPF of 1.77, which decreased to 1.10914 and 1.19 respectively at the end of the first cycle. Reloading 12 fresh FAs and shuffling 32 irradiated FAs within the core at this point increased the keff to 1.1584, sustaining criticality for an additional 540 EFPDs (the second cycle). Two more burnup cycles were simulated with the refueling patterns being established by evaluating the assembly discharge burnup and core power profile. Through a hybrid combination of in-out and out-in loading approaches, a high cumulative average discharge burnup exceeding 30 MWD/kg (over 40 MWD/kg for some assemblies) was achieved at the end of the fourth cycle (2160 EFPDs). Although the employed refueling patterns raised the power peaking factors (PPFs) at the beginning of each cycle, the core power distribution in general became more uniform and the PPF decreased as burnup progressed. Other than the beginning of the fourth cycle, the obtained PPF values were less than or around 2.00 even without the use of any control systems. Both the fuel and moderator temperature coefficients remained sufficiently negative throughout the burnup cycles. Further iterations of the implemented refueling schemes can be carried out depending on plant operational requirements.
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.