Li Wei , Liu Xiaojing , Chai Xiang , Liu Zijing , Zhao Pengcheng
{"title":"低浓缩铀核热推进反应堆的耦合多物理场分析","authors":"Li Wei , Liu Xiaojing , Chai Xiang , Liu Zijing , Zhao Pengcheng","doi":"10.1016/j.anucene.2025.111897","DOIUrl":null,"url":null,"abstract":"<div><div>The growing demand for high-performance propulsion systems in aerospace has highlighted that current multi-physics coupling technologies cannot accurately assess the performance and safety of low-enriched uranium nuclear thermal propulsion reactors (LEU-NTPRs) under extreme conditions. Accordingly, this study employs advanced multi-physics coupling methods to investigate the performance, safety, and thermoelastic behavior of LEU-NTPR assemblies and their core geometries under several extreme boundary conditions, providing a scientific basis for reactor design. By utilizing OpenFOAM, a multi-region neutron transport-conjugate heat transfer coupling solver is developed to perform pin-by-pin multi-physics coupling calculations for reactor assemblies and full-core geometries. Both the neutron transport and conjugate heat transfer equations are solved, and the resulting steady-state temperature distribution is used as the input for thermoelastic calculations. Thermoelastic analyses are conducted using the solid4Foam solver of OpenFOAM by assuming a small strain to evaluate the displacement and equivalent thermal stress distributions. The assembly coupled simulation shows a significantly improved prediction accuracy for fuel temperature compared to non-coupled methods. Core-coupled simulations confirm that the conceptual design adheres to physical and thermal engineering standards. A thermoelastic analysis reveals that the maximum thermal stress is ∼ 246 MPa, while the maximum fuel displacement reaches 7.1 mm. These findings suggest that thermal stress, particularly in regions with significant temperature gradients, can be a critical factor limiting core power output. By adjusting the core inlet flow rates, the maximum assembly temperature is controlled within safe limits while achieving uniform coolant outlet temperatures. The proposed multi-regional coupling approach enhances the prediction accuracy for the performance, safety, and thermoelastic characteristics of LEU-NTPRs under extreme conditions, while ensuring a high specific impulse in propulsion systems.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111897"},"PeriodicalIF":2.3000,"publicationDate":"2025-09-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Coupled multi-physics analysis of low-enriched uranium nuclear thermal propulsion reactors\",\"authors\":\"Li Wei , Liu Xiaojing , Chai Xiang , Liu Zijing , Zhao Pengcheng\",\"doi\":\"10.1016/j.anucene.2025.111897\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The growing demand for high-performance propulsion systems in aerospace has highlighted that current multi-physics coupling technologies cannot accurately assess the performance and safety of low-enriched uranium nuclear thermal propulsion reactors (LEU-NTPRs) under extreme conditions. Accordingly, this study employs advanced multi-physics coupling methods to investigate the performance, safety, and thermoelastic behavior of LEU-NTPR assemblies and their core geometries under several extreme boundary conditions, providing a scientific basis for reactor design. By utilizing OpenFOAM, a multi-region neutron transport-conjugate heat transfer coupling solver is developed to perform pin-by-pin multi-physics coupling calculations for reactor assemblies and full-core geometries. Both the neutron transport and conjugate heat transfer equations are solved, and the resulting steady-state temperature distribution is used as the input for thermoelastic calculations. Thermoelastic analyses are conducted using the solid4Foam solver of OpenFOAM by assuming a small strain to evaluate the displacement and equivalent thermal stress distributions. The assembly coupled simulation shows a significantly improved prediction accuracy for fuel temperature compared to non-coupled methods. Core-coupled simulations confirm that the conceptual design adheres to physical and thermal engineering standards. A thermoelastic analysis reveals that the maximum thermal stress is ∼ 246 MPa, while the maximum fuel displacement reaches 7.1 mm. These findings suggest that thermal stress, particularly in regions with significant temperature gradients, can be a critical factor limiting core power output. By adjusting the core inlet flow rates, the maximum assembly temperature is controlled within safe limits while achieving uniform coolant outlet temperatures. The proposed multi-regional coupling approach enhances the prediction accuracy for the performance, safety, and thermoelastic characteristics of LEU-NTPRs under extreme conditions, while ensuring a high specific impulse in propulsion systems.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"226 \",\"pages\":\"Article 111897\"},\"PeriodicalIF\":2.3000,\"publicationDate\":\"2025-09-23\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Annals of Nuclear Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0306454925007145\",\"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":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925007145","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}
Coupled multi-physics analysis of low-enriched uranium nuclear thermal propulsion reactors
The growing demand for high-performance propulsion systems in aerospace has highlighted that current multi-physics coupling technologies cannot accurately assess the performance and safety of low-enriched uranium nuclear thermal propulsion reactors (LEU-NTPRs) under extreme conditions. Accordingly, this study employs advanced multi-physics coupling methods to investigate the performance, safety, and thermoelastic behavior of LEU-NTPR assemblies and their core geometries under several extreme boundary conditions, providing a scientific basis for reactor design. By utilizing OpenFOAM, a multi-region neutron transport-conjugate heat transfer coupling solver is developed to perform pin-by-pin multi-physics coupling calculations for reactor assemblies and full-core geometries. Both the neutron transport and conjugate heat transfer equations are solved, and the resulting steady-state temperature distribution is used as the input for thermoelastic calculations. Thermoelastic analyses are conducted using the solid4Foam solver of OpenFOAM by assuming a small strain to evaluate the displacement and equivalent thermal stress distributions. The assembly coupled simulation shows a significantly improved prediction accuracy for fuel temperature compared to non-coupled methods. Core-coupled simulations confirm that the conceptual design adheres to physical and thermal engineering standards. A thermoelastic analysis reveals that the maximum thermal stress is ∼ 246 MPa, while the maximum fuel displacement reaches 7.1 mm. These findings suggest that thermal stress, particularly in regions with significant temperature gradients, can be a critical factor limiting core power output. By adjusting the core inlet flow rates, the maximum assembly temperature is controlled within safe limits while achieving uniform coolant outlet temperatures. The proposed multi-regional coupling approach enhances the prediction accuracy for the performance, safety, and thermoelastic characteristics of LEU-NTPRs under extreme conditions, while ensuring a high specific impulse in propulsion systems.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.