Acknowledgement
This study is sponsored by the National Natural Science Foundation of China (No. 12105170, 12135008). 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
- J.E. Hoogenboom, V.A. Khotylev, J.M. Tholammakkil, Generation of multi-group cross sections and scattering matrices with the Monte Carlo code MCNP5, in: J. Gonnord, T. Tajima (Eds.), Proceedings M&C+SNA 2007 Conference, ANS, Monterey, CA, USA, 2007, pp. 1-8, 15-19 April 2007.
- J.T. Goorley, M.R. James, T.E. Booth, J.S. Bull, L.J. Cox, J.W. Durkee Jr., J.S. Elson, M.L. Fensin, R.A.I. Forster, J.S. Hendricks, H.G.I. Hughes, R.C. Johns, B.C. Kiedrowski, R.L. Martz, S.G. Mashnik, G.W. McKinney, D.B. Pelowitz, R.E. Prael, J.E. Sweezy, L.S. Waters, T. Wilcox, A.J. Zukaitis, in: Initial MCNP6 Release Overview - MCNP6 Version 1.0, 2013, 1086758, https://doi.org/10.2172/1086758. LA-UR-13-22934.
- H.J. Shim, Y.C. Jin, J.S. Song, H.K. Chang, Generation of few group diffusion theory constants by Monte Carlo code, Trans. Am. Nucl. Soc. 99 (2008) 343-345.
- H.J. Park, H.J. Shim, H.G. Joo, C.H. Kim, Generation of few-group diffusion theory constants by Monte Carlo code McCARD, Nucl. Sci. Eng. 172 (2012) 66-77, https://doi.org/10.13182/NSE11-22.
- J. Leppanen, M. Pusa, E. Fridman, Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code, Ann. Nucl. Energy 96 (2016) 126-136, https://doi.org/10.1016/j.anucene.2016.06.007.
- E. Fridman, J. Leppanen, On the use of the Serpent Monte Carlo code for few-group cross section generation, Ann. Nucl. Energy 38 (2011) 1399-1405, https://doi.org/10.1016/j.anucene.2011.01.032.
- K. Wang, Z. Li, D. She, J. Liang, Q. Xu, Y. Qiu, J. Yu, J. Sun, X. Fan, G. Yu, Rmc - a Monte Carlo code for reactor core analysis, Ann. Nucl. Energy 82 (2015) 121-129, https://doi.org/10.1016/j.anucene.2014.08.048.
- 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) 928e944, https://doi.org/10.1080/00295450.2019.1571828.
- T.D.C. Nguyen, H. Lee, D. Lee, Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis, Nucl. Eng. Technol. 53 (2021) 2788-2802, https://doi.org/10.1016/j.net.2021.03.005.
- 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.
- 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.
- 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) 2733-2742, https://doi.org/10.1016/j.net.2020.05.029.
- H. Guo, Y. Wu, X. Jin, K. Feng, 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), 104484, https://doi.org/10.1016/j.pnucene.2022.104484.
- 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.G. Nelson, W. Boyd, P.K. Romano, The effect of the flux separability approximation on multigroup neutron transport, JNE 2 (2021) 86-96, https://doi.org/10.3390/jne2010009.
- 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. S1738573321006227.
- J.M. Ruggieri, J. Tommasi, J.F. Lebrat, C. Suteau, D. Plisson-Rieunier, C. De Saint Jean, G. Rimpault, J.C. Sublet, Eranos 2.1 : international code system for GEN IV fast reactor analysis, in: American Nuclear Society - ANS, 2006. La Grange Park (United States), Reno, USA, https://www.osti.gov/biblio/21021146. La Grange Park (United States), Reno, USA.
- 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.
- J.-F. Vidal, P. Archier, A. Calloo, P. Jacquet, J. Tommasi, An improved energy-collapsing method for core-reflector modelization in sfr core calculations using the paris platform, in: PHYSOR 2012, Tennessee, Knoxville, 2012, p. 15. USA.
- J.-F. Vidal, P. Archier, B. Faure, V. Jouault, J.-M. Palau, V. Pascal, G. Rimpault, F. Auffret, L. Graziano, E. Masiello, S. Santandrea, APOLLO3® homogenization techniques for transport core calculations - application to the ASTRID CFV core, Nucl. Eng. Technol. 49 (2017) 1379-1387, https://doi.org/10.1016/j.net.2017.08.014.
- R. Qiu, X. Ma, Q. Xu, J. Liu, Y. Chen, Development and verification of multigroup cross section process code TXMAT for fast reactor RBEC-M analysis, in: Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, American Society of Mechanical Engineers, Shanghai, China, 2017, V003T02A015, https://doi.org/10.1115/ICONE25-66550.