Acknowledgement
This work was partially supported by the National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIT). (No. NRF-2019M2D2A1A03058371). This research was partially supported by the project (L20S089000) by Korea Hydro & Nuclear Power Co. Ltd. This work was partially supported by Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea government (MOTIE) [RS-2023-00241302]. The data and information presented in the paper are part of an ongoing IAEA coordinated research project on "Neutronics Benchmark of CEFR Start-Up Tests - CRP-I31032".
References
- X. Huo, et al., Technical Specifications for Neutronics Benchmark of CEFR Start-Up Tests, China Institute of Atomic Energy, 2019. IAEA CRP-I31032.
- S. Choi, et al., Development of high-Fidelity neutron transport code STREAM, Comput. Phys. Commun. 264 (2021), 107915.
- J. Jang, S. Dzianisau, D. Lee, Development of nodal diffusion code RAST-V for vodo-vodyanoi Energetichesky reactor analysis, Nucl. Eng. Technol. 54 (2022) 3494-3515. https://doi.org/10.1016/j.net.2022.04.007
- J. Jang, et al., Analysis of rostov-II benchmark using conventional two-step code systems, Energies 15 (2022) 3318.
- 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. 54 (2022) 1789-1803. https://doi.org/10.1016/j.net.2021.10.038
- 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
- J.Y. Cho, C.H. Kim, Higher order polynomial expansion nodal method for hexagonal core neutronics analysis, Ann. Nucl. Eng. 25 (1998) 1021-1031. https://doi.org/10.1016/S0306-4549(97)00101-1
- J.Y. Cho, et al., Hexagonal CMFD formulation employing triangle-based polynomial expansion nodal kernel, in: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C), 2001. Salt Lake City, Utah, USA, September 9.
- M. Pusa, Rational approximations to the matrix exponential in burnup calculations, Nucl. Sci. Eng. 169 (2011) 155-167. https://doi.org/10.13182/NSE10-81
- T.Q. Tran, A. Cherezov, X. Du, J. Park, D. Lee, Development of hexagonal-Z geometry capability in RAST-K for fast reactor analysis, in: International Conference on Emerging Nuclear Energy Systems (ICENES), 2019. Bali, Indonesia, October 6-9.
- T.Q. Tran, S. Dzianisau, T.D.C. Nguyen, D. Lee, Verification of a depletion solver in RAST-K for fast reactor analysis, in: Korean Nuclear Society Virtual Autumn Meeting, 2020. R. Korea, Dec 16-18.
- T.Q. Tran, T.D.C. Nguyen, D. Lee, CEFR simulation using diffusion code system RAST-F, in: International Conference on Physics of Reactors (PHYSOR), 2022. Pittsburgh, USA, May 15-20.
- T.Q. Tran, D. Lee, Neutronic simulation of the CEFR experiments with the nodal diffusion code system RAST-F, Nucl. Eng. Technol. 54 (2022) 2635-2649. https://doi.org/10.1016/j.net.2022.01.027
- J. Yasinsky, A. Henry, Some numerical experiments concerning space-time reactor kinetics behavior, Nucl. Sci. Eng. 22 (1965) 171-181. https://doi.org/10.13182/NSE65-A20236
- J.P. Hamric, Spatial kinetics in large reactors, Trans. Am. Nucl. Soc. 8 (1965).
- Y. Chao, A. Attard, A resolution to the stiffness problem of reactor kinetics, Nucl. Sci. Eng. 90 (1985) 40-46. https://doi.org/10.13182/NSE85-A17429
- J. Sanchez, On the numerical solution of the point kinetics equations by generalized Runge-Kutta methods, Nucl. Sci. Eng. 103 (1989) 94-99. https://doi.org/10.13182/NSE89-A23663
- D.A. Meneley, K. Ott, E.S. Wiener, Space-Time Kinetics-The QX-1 Code, Argonne National Laboratory, 1968. ANL-7310.
- D.A. Meneley, K. Ott, E.S. Wiener, Fast Reactor Kinetics-The QX-1 Code, Argonne National Laboratory, 1971. ANL-7769.
- S.K. Chae, Review of computational methods for space-time reactor kinetics, J. Korean Nucl. Soc. 11 (1979) 219-229.
- T.M. Sutton, B.N. Aviles, Diffusion theory methods for spatial kinetics calculations, Prog. Nucl. Eng. 30 (1996) 119-182. https://doi.org/10.1016/0149-1970(95)00082-U
- T. Downar, et al., PARCS v3.0 U.S. NRC Core Neutronics Simulator Theory Manual, University of Michigan, USA, 2010.
- Y.A. Chao, Coarse mesh finite difference methods and applications, in: International Conference on Physics of Reactors, PHYSOR), Pittsburgh, Pennsylvania, USA, 2000. May 7-12.
- E. Fridman, X. Huo, Dynamic simulation of the CEFR control rod drop experiments with the Monte Carlo code Serpent, Ann. Nucl. Eng. 148 (2020), 107707.
- I. Pataki, et al., Validation of the KIKO3DMG neutronics code on the CEFR start-up tests, Ann. Nucl. Eng. 180 (2023), 109493.
- J. Leppanen, M. Pusa, T. Viitanen, V. Valtavirta, T. Kaltiaisenaho, The Serpent Monte Carlo code: status, development and applications in 2013, Ann. Nucl. Eng. 82 (2015) 142-150.
- X. Du, J. Choe, T.Q. Tuan, D. Lee, Neutronic simulation of China Experimental Fast Reactor start-up tests. Part I: SARAX code deterministic calculation, Ann. Nucl. Eng. 136 (2020), 107046.
- T.Q. Tran, J. Choe, X. Du, H. Lee, D. Lee, Neutronic simulation of China experimental fast reactor start-up tests part II: MCS code Monte Carlo calculation, Ann. Nucl. Eng. 148 (2020), 107710.
- Y. Hu, Y. Zhao, X. Chen, L. Xu, Proposing of a new fitting and iteration method (FIM) to correct measured reactor core reactivity, Nucl. Eng. Des. 254 (2013) 33-42. https://doi.org/10.1016/j.nucengdes.2012.08.034
- A.F. Henry, A.V. Vota, WIGL2-A Program for the Solution of the One-Dimensional, Two-Group, Space-Time Diffusion Equations Accounting for Temperature, Xenon, and Control Feedback, Bettis Atomic Power Lab., 1965. WAPD-TM-532.
- J.B. Yasinsky, M. Natelson, L.A. Hageman, TWIGL-A Program to Solve the Two-Dimensional, Two-Group, Space-Time Neutron Diffusion Equations with Temperature Feedback, Bettis Atomic Power Lab., 1968. WAPD-TM-743.
- W.M. Stacey, Space-time Nuclear Reactor Kinetics, Academic Press, New York, 1969.
- K.F. Hansen, et al., GAKIN: a One Dimensional Multigroup Kinetics Code, Calif. General Atomic Div., 1967. GA-7543.
- W.T. McCormick Jr., K.F. Hansen, Numerical Solution of the Two-Dimensional Time-dependent Multigroup Equations, Massachusetts Institute of Technology, 1969. MIT-3903-1.
- K.F. Hansen, J.H. Mason, GAKIN II : a One-Dimensional Multigroup Diffusion Theory Reactor Kinetics Code, Massachusetts Institute of Technology, 1973. COO2262-3.
- A.L. Wight, K.F. Hansen, D.R. Ferguson, Application on alternating-direction implicit methods to the space-dependent kinetics equations, Nucl. Sci. Eng. 44 (1971) 239-251. https://doi.org/10.13182/NSE71-A19671
- M.B. Chadwick, et al., ENDF/B-VII.1 nuclear data for science and Technology: cross sections, covariances, fission product yields and decay data, Nucl. Data Sheets 112 (2011) 2887-2996.
- E. Fridman, E. Shwageraus, Modeling of SFR cores with serpent-DYN3D codes sequence, Ann. Nucl. Eng. 53 (2013) 354-363. https://doi.org/10.1016/j.anucene.2012.08.006
- A. Kavenoky, The SPH homogenization method, in: Specialists' Meeting on Homogenization Methods in Reactor Physics, Lugano, Switzerland, 1978. November 13-15.