Acknowledgement
This work was supported by the Innovative Small Modular Reactor Development Agency grant funded by the Korea Government (MOTIE) (RS-2023-00259289).
References
- Y.S. Jung, C.B. Shim, C.H. Lim, H.G. Joo, Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers, Ann. Nucl. Energy 62 (2013) 357-374.
- M. Ryu, H.G. Joo, nTRACER whole core transport solutions to C5G7-TD benchmark, in: M&C 2017, Jeju, Korea, 2017.
- A. Rahman, H.C. Lee, D. Lee, High fidelity transient solver in STREAM based on multigroup coarse-mesh finite difference method, Nucl. Eng. Technol. 55 (9) (2023) 3301-3312.
- Q. Shen, Y. Wang, D. Jabaay, B. Kochunas, T. Downar, Transient analysis of C5G7-TD benchmark with MPACT, Ann. Nucl. Energy 125 (2019) 107-120.
- T.N. Nguyen, Y.S. Jung, T. Downar, C. Lee, Implementation of the transient fixedsource problem in the neutron transport code PROTEUS-MOC, Ann. Nucl. Energy 129 (2019) 199-206.
- M. Tatsumi, M. Tabuchi, K. Sato, Y. Kodama, Y. Ohoka, H. Nagano, Recent advancements in AEGIS/SCOPE2 and its verifications and validations, in: M&C 2017, Jeju, Korea, 2017.
- Y. Li, W. Yang, S. Wang, H. Wu, L. Cao, A three-dimensional PWR-core pin-by-pin analysis code NECP-Bamboo2.0, Ann. Nucl. Energy 144 (2020).
- Z. Li, J. Pan, B. Xia, S. Qiang, W. Lu, Q. Li, Verification of neutronics and thermalhydraulic coupled system with pin-by-pin calculation for PWR core, Nucl. Eng. Technol. 55 (9) (2023) 3213-3228.
- J. Yoon, H.C. Lee, H.G. Joo, H.S. Kim, High performance 3D pin-by-pin neutron diffusion calculation based on 2D/1D decoupling method for accurate pin power estimation, Nucl. Eng. Technol. 53 (11) (2021) 3543-3562.
- J.I. Yoon, H.G. Joo, Two-level coarse mesh finite difference formulation with multigroup source expansion nodal kernels, J. Nucl. Sci. Technol. 45 (7) (2008) 668-682.
- H. Hong, H.G. Joo, Thorough analyses and resolution of various errors in pinhomogenized multigroup core calculation, Ann. Nucl. Energy 163 (2021) 108502.
- A. Hebert, A consistent technique for the pin-by-pin homogenization of a pressurized water reactor assembly, Nucl. Sci. Eng. 113 (3) (1993) 227-238.
- H. Yu, H. Hong, J. Yoon, Application of modified 2D/1D decoupling method in the pin-wise core analysis, in: KNS 2023 Spring, Jeju, Korea, 2023.
- T. Kozlowski, T. Downar, PWR MOX/UO2 core transient benchmark [Online]. Available: https://www.oecd-nea.org/science/wprs/MOX-UOX-transients/benchmark_documents/final_report/mox-uo2-bench.pdf, 2006.
- J.I. Yoon, J.H. Kim, H.G. Joo, Investigation of multigroup effect in transient calculation to determine hottest pin enthalpy, in: M&C 2009, 2009. Saratoga Springs, New York, USA.
- T. Downar, et al., PARCS v2.6 U.S. NRC Core Neutronics Simulator THEORY MANUAL, 2004 [Online]. Available: https://engineering.purdue.edu/PARCS/Code/Manual/Theory/PDF/PARCS_TheoryManual.pdf.
- D. Bernard, A. Calame, J.-M. Palau, LWR-UOx Doppler reactivity coefficient: best estimate plus (nuclear and atomic sources of) uncertainties, in: M&C 2017, Jeju, Korea, 2017.
- G. Grandi, K. Smith, Z. Xu, J. Rhodes, Effect of CASMO-5 cross-section data and Doppler temperature definitions on LWR reactivity initiated accidents, in: PHYSOR 2010, 2010. Pittsburgh, Pennsylvania, USA.