과제정보
This work was supported by a research grant provided by KEPCO Nuclear Fuel Company (No. 12193).
참고문헌
- Y.S. Jung, H.G. Joo, Decoupled planar MOC solution for dynamic group constant generation in direct three-dimensional core calculations, Int. Conf. Math. Comput. Methods, React. Phys. (2009) 2157-2167.
- H.G. Joo, J.Y. Cho, K.S. Kim, C.C. Lee, S.Q. Zee, Methods and performance of a three-dimensional whole-core transport code DeCART, Int. Conf. Phys. React. 2004 (2004) 21-34.
- B. Kochunas, B. Collins, D. Jabaay, T.J. Downar, W.R. Martin, Overview of development and design of MPACT: Michigan parallel characteristics transport code, Int. Conf. Math. Comput. Methods, React. Phys. (2013) 42-53.
- W. Boyd, S. Shaner, L. Li, B. Forget, K. Smith, The OpenMOC method of characteristics neutral particle transport code, Ann. Nucl. Energy 68 (2014) 43-52, https://doi.org/10.1016/j.anucene.2013.12.012.
- S. Choi, D. Lee, Three-dimensional method of characteristics/diamond-difference transport analysis method in STREAM for whole-core neutron transport calculation, Comput. Phys. Commun. (2020), https://doi.org/10.1016/j.cpc.2020.107332, 107332.
- J.F. Briesmeister, MCNP-A General Monte Carlo N-Particle Transport Code, 2003 (No. LA-UR-03-1987), version 5.
- L.M. Petrie, Keno IV: an improved Monte Carlo criticality program (No. ORNL-4938). https://doi.org/10.2172/4158205, 2005.
- 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.
- H.J. Shim, B.S. Han, S.J. Jong, H.J. Park, C.H. Kim, McCARD: Monte Carlo code for advanced reactor design and analysis, Nucl. Eng. Technol. 44 (2012) 161-176, https://doi.org/10.5516/NET.01.2012.503.
- H. Lee, W. Kim, P. Zhang, M. Lemaire, A. Khassenov, J. Yu, Y. Jo, J. Park, D. Lee, Mcs - a Monte Carlo particle transport code for large-scale power reactor analysis, Ann. Nucl. Energy 139 (2020), https://doi.org/10.1016/j.anucene.2019.107276, 107276.
- D. Lee, T.J. Downar, Y. Kim, A nodal and finite difference hybrid method for pin-by-pin heterogeneous three-dimensional Light water reactor diffusion calculations, Nucl. Sci. Eng. 146 (2004) 319-339, https://doi.org/10.13182/NSE04-A2412.
- K.S. Smith, Multidimensional Nodal Transport Using the Simplified PL Method, Trans. Am. Nucl. Soc., 1986.
- M. Tatsumi, M. Tabuchi, K. Sato, Y. Kodama, Y. Ohoka, H. Nagano, Recent Advancements in AEGIS/SCOPE2 and Its Verifications and Validations, PHYSOR-2006: American Nuclear Society's Topical Meetings on Reactor Physics (2017). https://www.kns.org/files/int_paper/paper/MC2017_2017_9/P363S09-04TatsumiM.pdf.
- Y. Akio, T. Masahiro, K. Yasunori, Y. Yoshihiro, Improvement of the SPH method for pin-by-pin core calculations, J. Nucl. Sci. Technol. 41 (2004) 1155-1165, https://doi.org/10.1080/18811248.2004.9726344.
- Y. Li, W. Yang, S. Wang, H. Wu, L. Cao, A three-dimensional PWR-core pin-byp-in analysis code NECP-Bamboo 2.0, Ann. Nucl. Energy 144 (2020), https://doi.org/10.1016/j.anucene.2020.107507, 107507.
- H.G. Joo, D.A. Barber, G. Jiang, T.J. Downar. PARCS: Purdue Advanced Reactor Core Simulator PU/NE-08-26, Purdue University, 1998.
- Kaeri, APR1400 reactor core benchmark problem book. https://doi.org/10.1017/CBO9781107415324.004, 2019.
- A.T. Godfrey, VERA Core Physics Benchmark Progression Problem Specifications, Oak Ridge National Laboratory, 2014.
- Y. Saad, Iterative Methods for Sparse Linear Systems, 2000.
- H. Finnemann, F. Bennewitz, M.R. Wagner, Interface current techniques for multidimensional reactor calculations, Atomkernenergie 30 (1977) 123-128, accessed, https://inis.iaea.org/search/search.aspx?orig_q=RN:9350107. (Accessed 11 January 2021).
- K. Smith, An Analytic Nodal Method for Solving the Two-Group, Multidimensional, Static and Transient Neutron Diffusion Equations, MIT, 1979.
- T.M. Sutton, B.N. Aviles, Diffusion theory methods for spatial kinetics calculations, Prog. Nucl. Energy 30 (1996) 119-182, https://doi.org/10.1016/0149-1970(95)00082-U.
- K. Smith, Nodal method storage reduction by nonlinear iteration, Trans. Am. Nucl. Soc. 44 (1983) 265-266, accessed, https://inis.iaea.org/search/search. aspx?orig_q=RN:15010017. (Accessed 11 January 2021).
- H.G. Joo, T.J. Downar, An incomplete domain decomposition preconditioning method for nonlinear nodal kinetics calculations, Nucl. Sci. Eng. 123 (1996) 403-414, https://doi.org/10.13182/NSE96-A24203.
- K. Koebke, A new approach to homogenization and group condensation, in: IAEA Tech. Comm. Meet. Homog. Methods React. Phys., Lugano, Switzerland, 1978.
- K.S. Smith, Spatial Homogenization Methods for Light Water Reactors, MIT, 1980.
- 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.
- J.A. Turner, K. Clarno, M. Sieger, R. Bartlett, B. Collins, R. Pawlowski, R. Schmidt, R. Summers, The virtual environment for reactor Applications (VERA): design and architecture, J. Comput. Phys. 326 (2016) 544-568, https://doi.org/10.1016/J.JCP.2016.09.003.
- J.I. Yoon, H.G. Joo, Two-level coarse mesh finite difference formulation with multigroup source expansion nodal kernels, J. Nucl. Sci. Technol. 45 (2008) 668-682, https://doi.org/10.1080/18811248.2008.9711467.