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http://dx.doi.org/10.1016/j.net.2020.11.013

Analysis of C5G7-TD benchmark with a multi-group pin homogenized SP3 code SPHINCS  

Cho, Hyun Ho (Seoul National University)
Kang, Junsu (Seoul National University)
Yoon, Joo Il (KEPCO Nuclear Fuel Co. Ltd.)
Joo, Han Gyu (Seoul National University)
Publication Information
Nuclear Engineering and Technology / v.53, no.5, 2021 , pp. 1403-1415 More about this Journal
Abstract
The transient capability of a SP3 based pin-wise core analysis code SPHINCS is developed and verified through the analyses of the C5G7-TD benchmark. Spatial discretization is done by the fine mesh finite difference method (FDM) within the framework of the coarse mesh finite difference (CMFD) formulation. Pin size fine meshes are used in the radial fine mesh kernels. The time derivatives of the odd moments in the time-dependent SP3 equations are neglected. The pin homogenized group constants and Super Homogenization (SPH) factors generated from the 2D single assembly calculations at the unrodded and rodded conditions are used in the transient calculations via proper interpolation involving the approximate flux weighting method for the cases that involve control rod movement. The simplifications and approximations introduced in SPHINCS are assessed and verified by solving all the problems of C5G7-TD and then by comparing with the results of the direct whole core calculation code nTRACER. It is demonstrated that SPHINCS yields accurate solutions in the transient behaviors of core power and reactivity.
Keywords
Simplified $P_3$; Super-homogenization; Pinwise core analyses; Transient; Control rod cusping;
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1 P.S. Brantley, E.W. Larsen, The simplified P3 approximation, Nucl. Sci. Eng. 134 (2000) 1-21.   DOI
2 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.
3 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.   DOI
4 H.H. Cho, H. Hong, H.G. Lee, H.G. Joo, Preliminary development of simplified P3 based pin-by-pin core simulator, SPHINCS, in: KNS 2019 Spring, 2019. Jeju, Korea.
5 J. Kim, Y. Kim, Three-dimensional pin-resolved transient diffusion analysis of PWR core by the hybrid coarse-mesh finite difference algorithm, Nucl. Sci. Eng. 194 (2020) 1-13.   DOI
6 H.H. Cho, J. Kang, H.G. Joo, Transient capability of a multi-group pin homogenized SP3 code SPHINCS, in: KNS 2020, Spring, Jeju, Korea, 2020.
7 J.C. Gehin, A Quasi Static Polynomial Nodal Method for Nuclear Reactor Analysis, Ph. D thesis, Massachusetts Institute of Technology, 1992.
8 V.F. Boyarinov, A.E. Kondrushin, P.A. Fomichenko, Benchmark on deterministic time-dependent transport calculation without spatial homogenization, in: PHYSOR 2014, Kyoto, Japan, 2014.
9 K. Ogujiuba, J. Hou, K. Ivanov, Deterministic Time-dependent Neutron Transport Benchmark without Spatial Homogenization (C5G7-TD) Vol I : Kinetics Phase Final Report, Nuclear Energy Agency, Organization for Economic Co-operation and Development, 2019. NEA/NSC/DOC-xxx, 2020.
10 J.T. Hwang, N. Choi, H.G. Joo, Pin-by-pin 2D/1D SP3 FDM scheme with 3D assembly-wise CMFD acceleration, in: KNS 2019, Spring, Jeju, Korea, 2019.
11 H.G. Joo, D. Barber, G. Jiang, T. Downar, PARCS: a Multi-Dimensional Two-Group Reactor Kinetics Code Based on the Nolinear Analytic Nodal Method, 1998. PU/NE-98-26.
12 K.S. Smith, K.R. Renpe, J.D. Rhodes, J.G. Stevens, Enhancements of the studsvik core management system, in: Proc. Topl. Mtg. Advances in Reactor Physics, vol. 1, Charleston, South Carolina, 1992, p. 117. March 8-11, 1992.
13 A. Yamamoto, A simple and efficient control rod cusping model for three-dimensional pin-by-pin core calculations, Nucl. Technol. 145 (2004) 11-17.   DOI
14 C.B. Shim, Development of a High-Fidelity Core Simulator Employing Advanced SP3 Nodal Methods and Backward Differentiation Formula, Ph. D thesis, Seoul National University, 2015.
15 A. Yamamoto, Y. Kitamura, Y. Yamane, Cell homogenization methods for pin-by-pin core calculations tested in slab geometry, Ann. Nucl. Energy 31 (2004) 825-847.   DOI
16 M. Ryu, H.G. Joo, nTRACER whole core transport solutions to C5G7-TD benchmark, in: M&C 2017, Jeju, Korea, 2017.