References
- J. PARK et al., “RAST-K v2—Three-Dimensional Nodal Diffusion Code for Pressurized Water Reactor Core Analysis,” Energies, 13, 23, 6324 (2020); https://doi.org/https://doi.org/10.3390/en13236324.
- M. I. RADAIDEH, B. FORGET, and K. SHIRVAN, “Large-Scale Design Optimisation of Boiling Water Reactor Bundles with Neuroevolution,” Ann. Nucl. Energy, 160, 108355 (2021); https://doi.org/https://doi.org/10.1016/j.anucene.2021.108355.
- K. BENAALILOU et al., “Modeling and Simulation of a TRIGA MARK-II Research Reactor Using WIMSD-5B and CITATION Codes,” Appl. Radiat. Isot., 148, 64 (2019); https://doi.org/https://doi.org/10.1016/j.apradiso.2019.01.034.
- O. NOVAK et al., “Benchmark Evaluation of Zero-Power Critical Parameters for the Temelin VVER Nuclear Reactor Using SERPENT & NESTLE and MCNP,” Nucl. Eng. Des., 353, 110243 (2019); https://doi.org/https://doi.org/10.1016/j.nucengdes.2019.110243.
- T. DOWNAR, Y. XU, and V. SEKER, “PARCS V3.0 U.S. NRC Core Neutronics Simulator User Manual 3.0,” University of Michigan (2010).
- T. DOWNAR, Y. XU, and V. SEKER, “PARCS V3.0 U.S. NRC Core Neutronics Simulator Theory Manual,” University of Michigan (2009).
- J. Y. CHO et al., “Hexagonal CMFD Formulation Employing Triangle-Based Polynomial Expansion Nodal Kernel,” Proc. Int. Top. Mtg. on Mathematical Methods for Nuclear Applications (M&C 2001), Salt Lake City, Utah, September 9–13, 2001, American Nuclear Society ( 2001).
- “Non-Linear Triangle-Based Polynomial Expansion Nodal Method for Hexagonal Core Analysis,” KAERI/TR-1652/2000, Korea Atomic Energy Research Institute (2000).
- N. Z. CHO et al., “Extension of Analytic Function Expansion Nodal Method to Multigroup Problems in Hexagonal-Z Geometry,” Nucl. Sci. Eng., 126, 1, 35 (1997); https://doi.org/https://doi.org/10.13182/NSE97-A24455.
- N. Z. I. N. CHO, J. LEE, and N. ZIN CHO Ã, “Analytic Function Expansion Nodal (AFEN) Method in Hexagonal-Z Three-Dimensional Geometry for Neutron Diffusion Calculation,” J. Nucl. Sci. Technol., 43, 11, 1320 (2006); https://doi.org/https://doi.org/10.1080/18811248.2006.9711226.
- Y. S. JUNG, C. LEE, and M. A. SMITH, “PROTEUS-NODAL User Manual,” ANL/NE-18/4, Argonne National Laboratory (2018).
- M. K. JARADAT et al., “Development and Validation of PROTEUS-NODAL Transient Analyses Capabilities for Molten Salt Reactors,” Ann. Nucl. Energy, 160, 108402 (2021); https://doi.org/https://doi.org/10.1016/j.anucene.2021.108402.
- A. G. NELSON, M. A. SMITH, and F. HEIDET, “Verification of the Diffusion and Transport Solvers Within DIF3D for 3D Hexagonal Geometries,” EPJ Web Conf., 247, 10030 (2021); https://doi.org/https://doi.org/10.1051/epjconf/202124710030.
- M. R. OKTAVIAN and Y. XU, “Triangle-Based Quasi-Diffusion Nodal Method for Fast Reactor Analysis,” Trans. Am. Nucl. Soc., 123, 1351 (2020); https://doi.org/https://doi.org/10.13182/T123-33099.
- B. KOCHUNAS, Y. XU, and T. DOWNAR, “Development of the Triangular Nodal Method for Prismatic HTR Analysis,” Proc. PHYSOR 2010—Advances in Reactor Physics to Power the Nuclear Renaissance, Pittsburgh, Pennsylvania, May 9–14, 2010 (2010).
- Y. XU and T. DOWNAR, “Convergence Analysis of a CMFD Method Based on Generalized Equivalence Theory,” Proc. PHYSOR 2012—Advances in Reactor Physics—Linking Research, Industry, and Education, Knoxville, Tennessee, April 15–20, 2012 (2012).
- C. HAO, Y. XU, and T. J. DOWNAR, “Multi-Level Coarse Mesh Finite Difference Acceleration with Local Two-Node Nodal Expansion Method,” Ann. Nucl. Energy, 116, 105 (2018); https://doi.org/https://doi.org/10.1016/j.anucene.2018.02.002.
- P. PETKOV and S. MITTAGE, “NURESIM-SP1 Core Physics NURESIM Platform for Nuclear Reactor Simulation Specifications, Reference Solutions and DYN3D Solutions of the NURESIM-SP1 Benchmarks V1000-2D-C1, V1000-2D-C2 and V1000-2D-C3,” NUCTECH-2004-3.4.3.1-1 Milestone 19a Part—I and 19b—Part I,” European Commission Community Research (2007).
- G. TODOROVA et al., “NURESIM-SP1 Core Physics NURESIM Platform for Nuclear Reactor Simulation Solution of VVER Mathematical Benchmarks (I): V1000-2D-C1-tr by APOLLO2 MOC,” NUCTECH-2004-3.4.3.1-1 Milestone 19b2, European Commission Community Research (2008).
- M. PAPADIONYSIOU et al., “Assessment of nTRACER and PARCS Performance for VVER Configurations,” Nucl. Sci. Eng., 194, 11, 1056 (2020); https://doi.org/https://doi.org/10.1080/00295639.2020.1753418.
- J. LEPPÄNEN et al., “The Serpent Monte Carlo Code: Status, Development and Applications in 2013,” Ann. Nucl. Energy, 82, 142 (2015); https://doi.org/https://doi.org/10.1016/j.anucene.2014.08.024.
- J. LEPPÄNEN, M. PUSA, and E. FRIDMAN, “Overview of Methodology for Spatial Homogenization in the Serpent 2 Monte Carlo Code,” Ann. Nucl. Energy, 96, 126 (2016); https://doi.org/https://doi.org/10.1016/j.anucene.2016.06.007.
- E. FRIDMAN and J. LEPPÄNEN, “On the Use of the Serpent Monte Carlo Code for Few-Group Cross-Section Generation,” Ann. Nucl. Energy, 38, 6, 6 (2011); https://doi.org/https://doi.org/10.1016/j.anucene.2011.01.032.
- J. J. DUDERSTADT and L. J. HAMILTON, Nuclear Reactor Analysis, John Wiley & Sons, Inc. (1976).
- D. E. CULLEN, “Nuclear Data Preparation,” Handbook of Nuclear Engineering, pp. 279–425, Springer (2010).
- K. KOEBKE, “A New Approach to Homogenization and Group Condensation,” Proc. Specialists’ Mtg. on Homogenization Methods in Reactor Physics, November 1978, Vol. 231, p. 303 ( 1980).
- K. S. SMITH, “Spatial Homogenization Methods for Light Water Reactor Analysis,” PhD Thesis, Massachusetts Institute of Technology, Department of Nuclear Engineering (1980).
- K. S. SMITH, “Assembly Homogenization Techniques for Light Water Reactor Analysis,” Prog. Nucl. Energy, 17, 3, 303 (1986); https://doi.org/https://doi.org/10.1016/0149-1970(86)90035-1.
- E. FRIDMAN et al., “Axial Discontinuity Factors for the Nodal Diffusion Analysis of High Conversion BWR Cores,” Ann. Nucl. Energy, 62, 129 (2013); https://doi.org/https://doi.org/10.1016/j.anucene.2013.06.006.
- T. KOZLOWSKI et al., “Cell Homogenization Method for Pin-by-Pin Neutron Transport Calculations,” Nucl. Sci. Eng., 169, 1, 1 (2011); https://doi.org/https://doi.org/10.13182/NSE08-85.
- A. WARD, Y. XU, and T. DOWNAR, “Code for Generating the PARCS Cross Section Interface File PMAXS,” GenPMAXS-v6.3 Release, University of Michigan (2020).