多物理场耦合的数值反应堆技术调研
Technical Research Report on Multi-Physics Coupling of Numerical Reactor Technology
摘要: 本调研报告聚焦多物理场耦合的数值反应堆技术，全面梳理美国、欧洲、韩国、日本及中国在该领域的主要项目进展，涵盖美国I-NERI、CASL、NEAMS计划，欧洲NURE系列项目，以及中、韩、日各自的特色研发项目等。深入剖析关键技术问题，包括多物理耦合机制深化、高保真模型与算法突破、高性能计算与数据驱动融合困境、验证与不确定性量化体系短板等；并探讨多物理场深度融合与拓展、人工智能融合创新、多尺度建模与跨尺度模拟、量子计算赋能等前沿方向。总结各国发展态势，指出虽欧美领先、亚洲国家各具优势且中国发展迅速，但均面临共性难题且朝着共同前沿迈进，强调国际合作对推动技术发展保障核能产业的重要性。
Abstract: This research report focuses on multi-physics coupling of numerical reactor technology, providing a comprehensive review of major project advancements in the United States, Europe, South Korea, Japan, and China. It covers key initiatives such as the U.S. I-NERI, CASL, and NEAMS programs, Europe’s NURE series projects, and distinctive R&D projects in China, South Korea, and Japan. The report delves into critical technical challenges, including the deepening of multi-physics coupling mechanisms, breakthroughs in high-fidelity modeling and algorithms, the integration hurdles of high-performance computing and data-driven approaches, and shortcomings in verification and uncertainty quantification systems. Additionally, it explores cutting-edge directions such as deep multi-physics integration and expansion, AI-driven innovation, multi-scale modeling and cross-scale simulation, and the empowerment of quantum computing. The study summarizes global development trends, noting that although Europe and the U.S. lead the field, Asian countries each possess unique strengths, with China progressing rapidly, yet they all face common challenges and are advancing toward shared frontiers. The report emphasizes the importance of international collaboration in driving technological progress and ensuring the sustainability of the nuclear energy industry.
文章引用：何元雷, 汤春桃, 夏栓, 余建辉, 姜清尘. 多物理场耦合的数值反应堆技术调研[J]. 核科学与技术, 2025, 13(4): 193-202. https://doi.org/10.12677/nst.2025.134020

参考文献

[1] 吴宏春, 刘宙宇, 周欣宇, 等. 数值反应堆的研究现状与发展建议[J]. 原子能科学技术, 2022, 56(2): 193-212.
[2] Marcus, G.H. (2000) Considering the Next Generation of Nuclear Power Plants. Progress in Nuclear Energy, 37, 5-10. [Google Scholar] [CrossRef] 
[3] Peter, B.L. (2012) International Nuclear Energy Research Initiative: Fiscal Year 2012 Annual Report. Department of Energy Office of Nuclear Energy.
[4] Joo, H.G., Cho, J.Y., Kim, K.S., et al. (2004) Methods and Performance of a Three-Dimensional Whole-Core Transport Code DECART. PHYSOR 2004—The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, 25-29 April 2004, 21-34.
[5] Cho, J.Y., Han, T.Y., Park, H.J., Hong, S.G. and Lee, H.C. (2019) Improvement and Verification of the DECART Code for HTGR Core Physics Analysis. Nuclear Engineering and Technology, 51, 13-30. [Google Scholar] [CrossRef] 
[6] Park, H.J., Kim, S.J., Kwon, H. and Cho, J.Y. (2020) BEAVRS Benchmark Analyses by DECART Stand-Alone Calculations and Comparison with DECART/MATRA Multi-Physics Coupling Calculations. Nuclear Engineering and Technology, 52, 1896-1906. [Google Scholar] [CrossRef] 
[7] Han, T.Y., Lee, H.C., Cho, J.Y. and Jo, C.K. (2020) Improvement and Application of DECART/MUSAD for Uncertainty Analysis of HTGR Neutronic Parameters. Nuclear Engineering and Technology, 52, 461-468. [Google Scholar] [CrossRef] 
[8] Jung, Y.S., Shim, C.B., Lim, C.H. and Joo, H.G. (2013) Practical Numerical Reactor Employing Direct Whole Core Neutron Transport and Subchannel Thermal/Hydraulic Solvers. Annals of Nuclear Energy, 62, 357-374. [Google Scholar] [CrossRef] 
[9] Jang, J., Lee, H. and Lee, H.C. (2018) Criticality Benchmark of Mccard Monte Carlo Code for Light-Water-Reactor Fuel in Transportation and Storage Packages. Nuclear Engineering and Technology, 50, 1024-1036. [Google Scholar] [CrossRef] 
[10] CASL (2020) Consortium for Advanced Simulation of Light Water Reactors, CASL Phase Ⅱ Summary Report. ANS.
[11] Turner, J.A., Clarno, K., Sieger, M., Bartlett, R., Collins, B., Pawlowski, R., et al. (2016) The Virtual Environment for Reactor Applications (VERA): Design and Architecture. Journal of Computational Physics, 326, 544-568. [Google Scholar] [CrossRef] 
[12] US Department of Energy (2016) MPACT Theory Manual, Version 2.2.0.
https://info.ornl.gov/sites/publications/files/Pub69725.pdf
[13] Pandya, T., Johnson, S., Davidson, G., et al. (2015) SHIFT: A Massively Parallel Monte Carlo Radiation Transport Package. Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo (SNA + MC), Nashville, 19-23 April 2015.
[14] Gauld, I.C., Radulescu, G., Ilas, G., Murphy, B.D., Williams, M.L. and Wiarda, D. (2011) Isotopic Depletion and Decay Methods and Analysis Capabilities in Scale. Nuclear Technology, 174, 169-195. [Google Scholar] [CrossRef] 
[15] Avramova, M.N. and Salko, R.K. (2016) CTF Theory Manual. The Pennsylvania State University.
[16] Hales, J.D., Williamson, R.L., Novascone, S.R., Pastore G., Spencer, B.W., Stafford, D.S., et al. (2016) BISON Theory Manual: The Equations Behind Nuclear Fuel Analysis. Idaho National Laboratory.
[17] Kendrick, B. (2016) Mamba Theory Manual. Los Alamos National Laboratory.
[18] Lefebvre, R.A., Langley, B.R., Miller, P., et al. (2020) NEAMS Workbench Status and Capabilities. ORNL.
[19] Tonks, M.R., Gaston, D., Millett, P.C., Andrs, D. and Talbot, P. (2012) An Object-Oriented Finite Element Framework for Multiphysics Phase Field Simulations. Computational Materials Science, 51, 20-29. [Google Scholar] [CrossRef] 
[20] Delchini, M.O., Langley, B.R., Lefebvre, R.A., et al. (2018) Integration of the NEK5000 Computational Fluid Dynamics Code to the NEAMS Workbench. Oak Ridge National Laboratory.
[21] Stauff, N. (2019) Status of the NEAMS and ARC Neutronic Fast Reactor Tools Integration to the NEAMS Workbench. Argonne National Laboratory.
[22] Chauliac, C., Aragonés, J., Bestion, D., Cacuci, D.G., Crouzet, N., Weiss, F., et al. (2011) NURESIM—A European Simulation Platform for Nuclear Reactor Safety: Multi-Scale and Multi-Physics Calculations, Sensitivity and Uncertainty Analysis. Nuclear Engineering and Design, 241, 3416-3426. [Google Scholar] [CrossRef] 
[23] CEA, EDF R&D and Open CASCADE (2019) SALOME Platform.
https://www.salome-platform.org/
[24] Chanaron, B., Ahnert, C., Bestion, D., et al. (2010) The European Project NURISP for Nuclear Reactor Simulation. Transactions of the American Nuclear Society, 103, 617-672.
[25] Chanaron, B., Ahnert, C., Crouzet, N., Sanchez, V., Kolev, N., Marchand, O., et al. (2015) Advanced Multi-Physics Simulation for Reactor Safety in the Framework of the NURESAFE Project. Annals of Nuclear Energy, 84, 166-177. [Google Scholar] [CrossRef] 
[26] Chanaron, B. (2017) Overview of the NURESAFE European Project. Nuclear Engineering and Design, 321, 1-7. [Google Scholar] [CrossRef] 
[27] 曹良志, 邓力, 杨波, 等. CAP1400数值反应堆系统关键技术研究及示范应用[J]. 原子能科学技术, 2022, 56(2): 213-225.
[28] Chen, J., Liu, Z., Zhao, C., He, Q., Zu, T., Cao, L., et al. (2018) A New High-Fidelity Neutronics Code NECP-X. Annals of Nuclear Energy, 116, 417-428. [Google Scholar] [CrossRef] 
[29] Deng, L., Ye, T., Li, G., et al. (2014) 3-D Monte Carlo Neutron-Photon Transport Code JMCT and Its Algorithms., Proceedings of the International Conference on Physics of Reactors (PHYSOR2014), Kyoto, 28 September-3 October 2014.
[30] Gui, M., Tian, W., Wu, D., Chen, R., Wang, M. and Su, G.H. (2021) Parallelization and Application of SACOS for Whole Core Thermal-Hydraulic Analysis. Nuclear Engineering and Technology, 53, 3902-3909. [Google Scholar] [CrossRef] 
[31] 费敬然, 司胜义, 陈其昌. 燃料棒多物理数值模型研究与程序开发[J]. 核动力工程, 2016, 37(2): 7-12.
[32] 杨文, 胡长军, 刘天才, 等. 数值反应堆及CVR1.0研究进展[J]. 原子能科学技术, 2019, 53(10): 1821-1832.
[33] 李庆, 宫兆虎, 方浩宇, 等. 作为研究设计工具的数字化反应堆[J]. 南华大学学报(自然科学版), 2018, 32(3): 8-12.