{"title":"基于 SPN 方法的快堆 NCLFR-Oil 功率分配智能优化","authors":"Shaoning Shen, Wenshun Duan, Weixiang Wang, Aoguang Wu, Kefan Zhang, Hongli Chen","doi":"10.1016/j.nucengdes.2024.113580","DOIUrl":null,"url":null,"abstract":"<div><p>A custom-developed neutron transport module based on the COMSOL finite element solver was created to enable efficient optimization and parameter evaluation in core design, and it can be integrated with other built-in modules for enhanced capabilities. This work began by establishing a practical foundation for a multi-dimensional SP<sub>N</sub> method using the PDE solver, capable of simulating both steady-state (k-eigenvalue) and time-dependent transport problems. The steady-state solver showed good agreement with 3D TAKEDA and 2D C5G7 benchmarks, while the transient solver was well-validated with TWIGL and LMW benchmarks. For modeling the self-designed fast reactor NCLFR-Oil, OpenMC was used to generate few-group constants, which were then imported into COMSOL’s SP<sub>3</sub> neutron transport module as equation coefficients. The SP<sub>3</sub> model’s capability to simulate the core’s physical field was validated by testing eigenvalues, control rod worth, the power and neutron flux distribution. Sensitivity analysis was performed using COMSOL’s uncertainty quantification module to assess the impact of control rod positions on core eigenvalues and power distribution, refining the parameter space for optimization and enhancing efficiency. To further improve optimization efficiency, a surrogate model based on “Polynomial Chaos Expansion” was employed to approximate the core’s physical model, predicting relationships between input parameters and optimization objectives. This model proved more efficient than the gradient-free “Coordinate Search” method, reducing computational resource consumption. The optimization results showed a significant reduction in the custom power flattening factor, bringing more power factors closer to the target value of 1.</p></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"429 ","pages":"Article 113580"},"PeriodicalIF":1.9000,"publicationDate":"2024-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Intelligent optimization of power distribution for fast reactor NCLFR-Oil based on SPN method\",\"authors\":\"Shaoning Shen, Wenshun Duan, Weixiang Wang, Aoguang Wu, Kefan Zhang, Hongli Chen\",\"doi\":\"10.1016/j.nucengdes.2024.113580\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>A custom-developed neutron transport module based on the COMSOL finite element solver was created to enable efficient optimization and parameter evaluation in core design, and it can be integrated with other built-in modules for enhanced capabilities. This work began by establishing a practical foundation for a multi-dimensional SP<sub>N</sub> method using the PDE solver, capable of simulating both steady-state (k-eigenvalue) and time-dependent transport problems. The steady-state solver showed good agreement with 3D TAKEDA and 2D C5G7 benchmarks, while the transient solver was well-validated with TWIGL and LMW benchmarks. For modeling the self-designed fast reactor NCLFR-Oil, OpenMC was used to generate few-group constants, which were then imported into COMSOL’s SP<sub>3</sub> neutron transport module as equation coefficients. The SP<sub>3</sub> model’s capability to simulate the core’s physical field was validated by testing eigenvalues, control rod worth, the power and neutron flux distribution. Sensitivity analysis was performed using COMSOL’s uncertainty quantification module to assess the impact of control rod positions on core eigenvalues and power distribution, refining the parameter space for optimization and enhancing efficiency. To further improve optimization efficiency, a surrogate model based on “Polynomial Chaos Expansion” was employed to approximate the core’s physical model, predicting relationships between input parameters and optimization objectives. This model proved more efficient than the gradient-free “Coordinate Search” method, reducing computational resource consumption. The optimization results showed a significant reduction in the custom power flattening factor, bringing more power factors closer to the target value of 1.</p></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"429 \",\"pages\":\"Article 113580\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-09-18\",\"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/S0029549324006800\",\"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/S0029549324006800","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}
Intelligent optimization of power distribution for fast reactor NCLFR-Oil based on SPN method
A custom-developed neutron transport module based on the COMSOL finite element solver was created to enable efficient optimization and parameter evaluation in core design, and it can be integrated with other built-in modules for enhanced capabilities. This work began by establishing a practical foundation for a multi-dimensional SPN method using the PDE solver, capable of simulating both steady-state (k-eigenvalue) and time-dependent transport problems. The steady-state solver showed good agreement with 3D TAKEDA and 2D C5G7 benchmarks, while the transient solver was well-validated with TWIGL and LMW benchmarks. For modeling the self-designed fast reactor NCLFR-Oil, OpenMC was used to generate few-group constants, which were then imported into COMSOL’s SP3 neutron transport module as equation coefficients. The SP3 model’s capability to simulate the core’s physical field was validated by testing eigenvalues, control rod worth, the power and neutron flux distribution. Sensitivity analysis was performed using COMSOL’s uncertainty quantification module to assess the impact of control rod positions on core eigenvalues and power distribution, refining the parameter space for optimization and enhancing efficiency. To further improve optimization efficiency, a surrogate model based on “Polynomial Chaos Expansion” was employed to approximate the core’s physical model, predicting relationships between input parameters and optimization objectives. This model proved more efficient than the gradient-free “Coordinate Search” method, reducing computational resource consumption. The optimization results showed a significant reduction in the custom power flattening factor, bringing more power factors closer to the target value of 1.
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.