Acknowledgement
This work was supported by the National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIT). (No. NRF-2019M2D2A1A03058371).
References
- J. Jang, C. Kong, B. Ebiwonjumi, Y. Jo, D. Lee, Uncertainties of PWR spent nuclear fuel isotope inventory for back-end cycle analysis with Stream/RAST-K, Ann. Nucl. Energy 158 (2021), https://doi.org/10.1016/j.anucene.2021.108267.
- J. Jang, C. Kong, B. Ebiwonjumi, A. Cherezov, Y. Jo, D. Lee, Uncertainty quantification in decay heat calculation of spent nuclear fuel by Stream/RAST-K, Nucl. Eng. Technol. 53 (2021) 2803-2815, https://doi.org/10.1016/j.net.2021.03.010.
- S. Choi, C. Lee, D. Lee, Resonance treatment using pin-based pointwise energy slowing-down method, J. Comp. Physiol. 330 (2017) 134-155, https://doi.org/10.1016/j.jcp.2016.11.007.
- B.T. Rearden, M.A. Jessee, SCALE Code System, Oak Ridge National Laboratory, 2017.
- M.B. Chadwick, M. Herman, P. Oblozinsky, M.E. Dunn, Y. Danon, A.C. Kahler, D. L. Smith, B. Pritychenko, G. Arbanas, R. Arcilla, R. Brewer, D.A. Brown, R. Capote, A.D. Carlson, Y.S. Cho, H. Derrien, K. Guber, G.M. Hale, S. Hoblit, S. Holloway, T. D. Johnson, T. Kawano, B.C. Kiedrowski, H. Kim, S. Kunieda, N.M. Larson, L. Leal, J.P. Lestone, R.C. Little, E.A. McCutchan, R.E. MacFarlane, M. MacInnes, C. M. Mattoon, R.D. McKnight, S.F. Mughabghab, G.P.A. Nobre, G. Palmiotti, A. Palumbo, M.T. Pigni, V.G. Pronyaev, R.O. Sayer, A.A. Sonzogni, N.C. Summers, P. Talou, I.J. Thompson, A. Trkov, R.L. Vogt, S.C. van der Marck, A. Wallner, M. C. White, D. Wiarda, P.G. Young, 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, https://doi.org/10.1016/j.nds.2011.11.002.
- D B, Kothe. CASL: The consortium for advanced simulation of light water reactors A DOE energy innovation hub. https://www.ne.anl.gov/mmsnf/presentations/Kothe.pdf, Oak Ridge National Laboratory.
- R.N. Bratton, M. Avramova, K. Ivanov, N. R, OECD/NEA benchmark for uncertainty analysis in modeling (UAM) for lwrs - summary and discussion of neutronics cases (phase I), Nucl. Eng. Technol. 46 (2014) 313-342, https://doi.org/10.5516/NET.01.2014.710.
- J. Jang, M. Hursin, W. Lee, A. Pautz, M. Papadionysiou, H. Ferroukhi, D. Lee, Analysis of Rostov-II benchmark using conventional two-step code systems, Energies 15 (2022) 3318, https://doi.org/10.3390/en15093318.
- 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.
- S. Choi, W. Kim, J. Choe, W. Lee, H. Kim, B. Ebiwonjumi, E. Jeong, K. Kim, D. Yun, H. Lee, D. Lee, Development of high-fidelity neutron transport code STREAM, Comput. Phys. Commun. 264 (2021), https://doi.org/10.1016/j.cpc.2021.107915.
- J. Park, J. Jang, H. Kim, J. Choe, D. Yun, P. Zhang, A. Cherezov, D. Lee, R.-K. Lee, RAST-K v2-three-dimensional nodal diffusion code for pressurized water reactor core analysis, Energies 13 (2020) 6324, https://doi.org/10.3390/en13236324.
- R.J.J. Stamm'ler, M.J. Abbate, Methods of Steady-State Reactor Physics in Nuclear Design, Academic Press Inc. (LONDON) LTD, 1983. ISBN 0-12-663320-7.
- D. Knott, A. Yamamoto, Lattice physics computations, in: D.G. Cacuci (Ed.), Handbook of Nuclear Engineering, Springer, 2010, pp. 913-1239.
- J. Jang, Development of Nodal Diffusion Code for VVER and HTGR Analysis with Advanced Semi Analytic Nodal Method, Ulsan National Institute of Science and Technology, 2023 doctoral thesis.
- D.W. Muir, R.M. Boicourt, A.C. Kahler, J.L. Conlin, W. Haeck, The NJOY Nuclear Data Processing System, Version 2016, LA-UR-17-20093, Los Alamos National Laboratory, 2016.
- J. Jang, B. Ebiwonjumi, W. Kim, A. Cherezov, J. Park, D. Lee, Verification and validation of isotope inventory prediction for back-end cycle management using two-step method, Nucl. Eng. Technol. 53 (2021) 2104-2125, https://doi.org/10.1016/j.net.2021.01.009.
- J. Jang, B. Ebiwonjumi, W. Kim, J. Park, J. Choe, D. Lee, Validation of spent nuclear fuel decay heat calculation by a two-step method, Nucl. Eng. Technol. 53 (2021) 44-60, https://doi.org/10.1016/j.net.2020.06.028.
- J. Choe, S. Choi, P. Zhang, J. Park, W. Kim, H.C. Shin, H.S. Lee, J. Jung, D. Lee, Verification and validation of Stream/RAST-K for PWR analysis, Nucl. Eng. Technol. 51 (2019) 356-368, https://doi.org/10.1016/j.net.2018.10.004.
- R.J.J. Stamm'ler, M.J. Abbate, Methods of Steady-State Reactor Physics in Nuclear Design, Academic Press Inc. (LONDON) LTD, 1983. ISBN 0-12-663320-7.
- D. Knott, A. Yamamoto, Lattice physics computations, in: D.G. Cacuci (Ed.), Handbook of Nuclear Engineering, Springer, US, Boston, Massachusetts, 2010, pp. 913-1239.
- A. Yamamoto, K. Kinoshita, T. Watanabe, T. Endo, Y. Kodama, Y. Ohoka, T. Ushio, H. Nagano, Uncertainty quantification of LWR core characteristics using random sampling method, Nucl. Sci. Eng. 181 (2015) 160-174, https://doi.org/10.13182/NSE14-152.
- G. Errorj, Chiba: A Code to Process Neutron-Nuclide Reaction Cross Section Covariance, Japan Atomic Energy Agency, 2007, version 2.3.
- K. Kosako, N. Yamano, Preparation of a covariance processing system for the evaluated nuclear data file, JENDL, (III),', Japan Nuclear Cycle De-Velopment Institute, 1999, pp. 1-114. JNC TJ 9440 99-003, vol.3, [in Japanese], https://jopss.jaea.go.jp/pdfdata/JNC-TJ9440-99-003.pdf.
- D. Wiarda, M.E. Dunn, N.M. Greene, M.L. Williams, C. Celik, L.M. Petrie, AMPX-6: a modular code system for processing ENDF/B, in: ORNL/TM-2016/43, Oak Ridge National Laboratory, 2016.
- G. Ilas, H. Liljenfeldt, Decay heat uncertainty for BWR used fuel due to modeling and nuclear data uncertainties, Nucl. Eng. Des. 319 (2017) 176e184, https://doi.org/10.1016/j.nucengdes.2017.05.009.
- V.C. Klema, A.J. Laub, The singular value decomposition: its computation and some applications, IEEE Trans. Automat. Control 25 (1980). https://ieeexplore.ieee.org/document/1102314. 102314
- T. Zhu, Sampling-Based Nuclear Data Uncertainty Quantification for Continuous Energy Monte Carlo Codes, Ecole Polytechnique Federale de Lausanne, 2015, https://doi.org/10.5075/epfl-thesis-6598.
- N.J. Quartemont, A.A. Bickley, J.E. Bevins, Nuclear data covariance analysis in radiation-trransport simulations utilizing SCALE sampler and the IRDFF nuclear data library, IEE, transactions on nuclear, Science 67 (2020) 482-491.
- K.A. Kinoshita, T. Yamamoto, Y. Endo, Y. Kodama, T. Ohoka, H. Ushio, Nagano. Uncertainty Quantification of Nutronics Characteristics Using Latin HyperCube Sampling Method, 2014. September 28, PHYSOR, Kyoto, Japan.
- R.E. MacFarlane, Covariance plots for ENDF/B-VII.1. https://t2.lanl.gov/nis/data/endf/covVII.1/, Los Alamos National Laboratory.
- J. Jang, Development of Nodal Diffusion Code for VVER and HTGR Analysis with Advanced Semi Analytic Nodal Method, Ulsan National Institute of Science and Technology, 2023 doctoral thesis.
- K.M. Ivanov, S. Avramova, I. Kamerow, E. Kodeli, E. Sartori, O. Ivanov, Cabellos., Benchmark for Uncertainty Analysis in Modelling (Uam) for Design, Operation and Safety Analysis of LWRs, I: Specification and Support Data for the Neutronics Cases (Phase I), OECD Nuclear Energy Agency, June 2016.
- Y. Bilodid, E. Fridman, T. Lotsch, X2 VVER-1000 benchmark revision: fresh HZP core state and the reference Monte Carlo solution, Ann. Nucl. Energy 144 (2020), https://doi.org/10.1016/j.anucene.2020.107558.
- J. Leppanen, M. Pusa, T. Viitanen, V. Valtavirta, T. Kaltiaisenaho, The Serpent Monte Carlo code: status, development and applications in 2013, Ann. Nucl. Energy 82 (2015) 142-150, https://doi.org/10.1016/j.anucene.2014.08.024.
- M.B. Chadwick, P. Oblozinsky, M. Herman, N.M. Greene, R.D. McKnight, D. L. Smith, P.G. Young, R.E. MacFarlane, G.M. Hale, S.C. Frankle, A.C. Kahler, T. Kawano, R.C. Little, D.G. Madland, P. Moller, R.D. Mosteller, P.R. Page, P. Talou, H. Trellue, M.C. White, W.B. Wilson, R. Arcilla, C.L. Dunford, S.F. Mughabghab, B. Pritychenko, D. Rochman, A.A. Sonzogni, C.R. Lubitz, T.H. Trumbull, J. P. Weinman, D.A. Brown, D.E. Cullen, D.P. Heinrichs, D.P. McNabb, H. Derrien, M. E. Dunn, N.M. Larson, L.C. Leal, A.D. Carlson, R.C. Block, J.B. Briggs, E.T. Cheng, H.C. Huria, M.L. Zerkle, K.S. Kozier, A. Courcelle, V. Pronyaev, S.C. van der Marck, ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology, nuclear data sheets, next generation evaluated nuclear data library for nuclear science and technology, Nucl. Data Sheets 107 (2006) 2931-3060, https://doi.org/10.1016/j.nds.2006.11.001.
- E. Canuti, A. Petruzzi, F. D'Auria, T. Kozlowski, Sensitivity studies for the exercise I-1 of the OECD/UAM benchmark, Science and Technology of Nuclear Installations 2012 (2012) 10, https://doi.org/10.1155/2012/817185, 817185.
- H.J. Park, McCARD/MIG stochastic sampling calculations for nuclear cross section sensitivity and uncertainty analysis, Nucl. Eng. Technol. 54 (2022) 4272-4279, https://doi.org/10.1016/j.net.2022.06.012.
- A. Labarile, N. Olmo, R. Miro, T. Barrachina, G. Verdu, Comparison of SERPENT and SCALE methodology for LWRs transport calculations and additionally uncertainty analysis for cross section perturbation with SAMPLER module, EPJ Nuclear, Sci. Technol. 2 (2016), https://doi.org/10.1051/epjn/e2016-50002-7.
- L. Mercatali, K. Ivanov, V.H. Sanchez, SCALE modeling of selected neutronics test problems within the OECD UAM LWR's benchmark, Sci. Technol. Nucl. Installations. 2013 (2013) 1-11, https://doi.org/10.1155/2013/573697.
- C. Arenas, R. Bratton, F. Reventos, K. Ivanov, Uncertainty analysis of light water reactor fuel lattices, Sci. Technol. Nucl. Installations. 2013 (2013) 1-10, https://doi.org/10.1155/2013/437409.
- B.T. Rearden, M.L. Williams, M.A. Jessee, D.E. Mueller, D.A. Wiarda, Sensitivity and Uncertainty Analysis Capabilities and Data in SCALE, vol. 174, 2011, https://doi.org/10.13182/NT174-236.
- SCALE, A modular code system for performing standardized computer analyses licensing evaluation, NUREG/CR-0200, Rev.4 (ORNL/NUREG/CSD-2R4), Vols. and 111 (April 1995). RSIC code package CCC-545, version 4.2.