Acknowledgement
This study is sponsored by National Natural Science Foundation of China (No. 12105170, 12135008), Science and Technology on Reactor System Design Technology Laboratory and the Shanghai Sailing Program (No. 20YF1420700). The computations in this paper were run on the π-2.0 cluster supported by the Center for High-Performance Computing at Shanghai Jiao Tong University.
References
- E. Nikitin, E. Fridman, K. Mikityuk, Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems, Ann. Nucl. Energy 75 (2015) 492-497, https://doi.org/10.1016/j.anucene.2014.08.054.
- T.Q. Tran, A. Cherezov, X. Du, D. Lee, Verification of a two-step code system MCS/RAST-F to fast reactor core analysis, Nucl. Eng. Technol. (2021), https://doi.org/10.1016/j.net.2021.10.038.
- N. Martin, R. Stewart, S. Bays, A multiphysics model of the versatile test reactor based on the MOOSE framework, Ann. Nucl. Energy 172 (2022), 109066, https://doi.org/10.1016/j.anucene.2022.109066.
- H. Guo, E. Garcia, B. Faure, L. Buiron, P. Archier, P. Sciora, G. Rimpault, Advanced method for neutronic simulation of control rods in sodium fast reactors: numerical and experimental validation, Ann. Nucl. Energy 129 (2019) 90-100. https://doi.org/10.1016/j.anucene.2019.01.042
- H. Guo, K. Feng, Y. Wu, X. Jin, X. Huo, H. Gu, Preliminary verification of multigroup cross-sections generation and locally heterogeneous transport calculation using OpenMC with CEFR start-up tests benchmark, Prog. Nucl. Energy 154 (2022).
- P.K. Romano, B. Forget, The OpenMC Monte Carlo particle transport code, Ann. Nucl. Energy 51 (2013) 274-281, https://doi.org/10.1016/j.anucene.2012.06.040.
- A.V. Zrodnikov, G.I. Toshinsky, O.G. Komlev, YuG. Dragunov, V.S. Stepanov, N.N. Klimov, V.N. Generalov, I.I. Kopytov, V.N. Krushelnitsky, Innovative nuclear technology based on modular multi-purpose lead-bismuth cooled fast reactors, Prog. Nucl. Energy 50 (2008) 170-178, https://doi.org/10.1016/j.pnucene.2007.10.025.
- A.V. Zrodnikov, G.I. Toshinsky, O.G. Komlev, V.S. Stepanov, N.N. Klimov, SVBR100 module-type fast reactor of the IV generation for regional power industry, J. Nucl. Mater. 415 (2011) 237-244, https://doi.org/10.1016/j.jnucmat.2011.04.038.
- J.M. Ruggieri, J. Tommasi, J.F. Lebrat, C. Suteau, D. Plisson-Rieunier, G. Rimpault, J.C. Sublet, ERANOS 2.1 : International Code System for GEN IV Fast Reactor Analysis, 2006, p. 9.
- W. Boyd, A. Nelson, P.K. Romano, S. Shaner, B. Forget, K. Smith, Multigroup cross-section generation with the OpenMC Monte Carlo particle transport code, Nucl. Technol. 205 (2019) 928-944, https://doi.org/10.1080/00295450.2019.1571828.
- A. Nelson, Improved Convergence Rate of Multi-Group Scattering Moment Tallies for Monte Carlo Neutron Transport Codes, Ph.D., University of Michigan, 2014. https://www.proquest.com/docview/1652006060/abstract/9CF0D90C6C644A4PQ/1. (Accessed 12 October 2022). accessed.
- A.G. Nelson, W. Boyd, P.K. Romano, The effect of the flux separability approximation on multigroup neutron transport, J. Nucl. Eng. 2 (2021) 86-96, https://doi.org/10.3390/jne2010009.
- A. Hebert, A consistent technique for the pin-by-pin homogenization of a pressurized water reactor assembly, Nucl. Sci. Eng. 113 (1993) 227-238, https://doi.org/10.13182/NSE92-10.
- A. Hebert, G. Mathonniere, Development of a third-generation super-homogeneisation method for the homogenization of a pressurized water reactor assembly, Nucl. Sci. Eng. 115 (1993) 129-141, https://doi.org/10.13182/NSE115-129.
- E. Nikitin, E. Fridman, K. Mikityuk, On the use of the SPH method in nodal diffusion analyses of SFR cores, Ann. Nucl. Energy 85 (2015) 544-551. https://doi.org/10.1016/j.anucene.2015.06.007.
- T.M. Pandya, F. Bostelmann, M. Jessee, J. Ortensi, Two-step neutronics calculations with Shift and Griffin for advanced reactor systems, Ann. Nucl. Energy 173 (2022), 109131, https://doi.org/10.1016/j.anucene.2022.109131.
- V. Laboure, Y. Wang, J. Ortensi, S. Schunert, F. Gleicher, M. DeHart, R. Martineau, Hybrid super homogenization and discontinuity factor method for continuous finite element diffusion, Ann. Nucl. Energy 128 (2019) 443-454, https://doi.org/10.1016/j.anucene.2019.01.003.
- C.-S. Lin, W.S. Yang, An assessment of the applicability of multigroup cross sections generated with Monte Carlo method for fast reactor analysis, Nucl. Eng. Technol. 52 (2020) 2733-e2742, https://doi.org/10.1016/j.net.2020.05.029.
- H. Guo, L. Buiron, P. Sciora, T. Kooyman, Optimization of reactivity control in a small modular sodium-cooled fast reactor, Nucl. Eng. Technol. 52 (2020) 1367-1379. https://doi.org/10.1016/j.net.2019.12.015
- K. Fujimura, S. Itooka, T. Nitawaki, Fast reactor core concepts for minor actinide transmutation using solid moderator. https://www.osti.gov/etdeweb/biblio/22027493, 2011. (Accessed 26 October 2020).