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http://dx.doi.org/10.1016/j.net.2017.06.016

Recent developments in the GENESIS code based on the Legendre polynomial expansion of angular flux method  

Yamamoto, Akio (Nagoya University)
Giho, Akinori (Nagoya University)
Endo, Tomohiro (Nagoya University)
Publication Information
Nuclear Engineering and Technology / v.49, no.6, 2017 , pp. 1143-1156 More about this Journal
Abstract
This paper describes recent development activities of the GENESIS code, which is a transport code for heterogeneous three-dimensional geometry, focusing on applications to reactor core analysis. For the treatment of anisotropic scattering, the concept of the simplified Pn method is introduced in order to reduce storage of flux moments. The accuracy of the present method is verified through a benchmark problem. Next, the iteration stability of the GENESIS code for the highly voided condition, which would appear in a severe accident (e.g., design extension) conditions, is discussed. The efficiencies of the coarse mesh finite difference and generalized coarse mesh rebalance acceleration methods are verified with various stabilization techniques. Use of the effective diffusion coefficient and the artificial grid diffusion coefficients are found to be effective to stabilize the acceleration calculation in highly voided conditions.
Keywords
Acceleration; Anisotropic scattering; C5G7 Benchmark Problem; GENESIS; Simplified Pn; Stability;
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1 B. Kochunas, B. Collins, D. Jabaay, T.J. Downar, W.R. Martin, Overview of development and design of MPACT: Michigan Parallel Characteristics Transport Code, in: Proc. M&C2013, Sun Valley, ID, May 5-9, 2013 (CD-ROM).
2 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
3 M. Ryu, Y.S. Junga, H.H. Cho, H.G. Joo, Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code, J. Nucl. Sci. Technol. 52 (2015) 961-969.   DOI
4 M. Hursin, Full Core, Heterogeneous, Time Dependent Neutron Transport Calculations with the 3D Code DeCart (Ph.D. thesis), UC Berkeley, 2010.
5 J.B. Taylor, D. Knott, A.J. Baratta, A method of characteristics solution to the OECD/NEA 3D neutron transport benchmark problem, in: Proc. M&C + SNA 2007, Monterey, CA, 2007.
6 Z. Liu, H. Wu, L. Cao, Q. Chen, Y. Li, A new three-dimensional method of characteristics for neutron transport calculation,, Ann. Nucl. Energy 38 (2011) 447.   DOI
7 B. Kochunas, T.J. Downar, Z. Liu, Parallel 3-D method of characteristics in MPACT, in: Proc. M&C2013, Sun Valley, ID, May 5-9, 2013 (CD-ROM).
8 A. Giho, K. Sakai, Y. Imamura, H. Sakurai, K. Miyawaki, Development of axially simplified method of characteristics in three-dimensional geometry, J. Nucl. Sci. Technol. 45 (2003) 985.
9 Y. Kato, T. Endo, A. Yamamoto, Development of Legendre expansion of angular flux method for 3D MOC calculation, in: Proc. PHYSOR2014, JAEA-Conf 2014-003, Japan Atomic Energy Agency, 2014.
10 A. Yamamoto, A. Giho, Y. Kato, T. Endo, GENESIS - a three-dimensional heterogeneous transport solver based on the Legendre polynomial expansion of angular flux method, Nucl. Sci. Eng. 186 (2017) 1-22.   DOI
11 K.S. Smith, R. Ferrer, J.D. Rhodes, Linear source approximation in CASMO5, in: Proc. PHYSOR2012, Knoxville, TN, USA, April 15-20, 2012 (CD-ROM).
12 T. Jevremovic, J. Vujic, K. Tsuda, ANEMONA-a neutron transport code for general geometry reactor assemblies based on the method of characteristics and R-function solid modeler, Ann. Nucl. Energy 28 (2001) 125.   DOI
13 S. Kosaka, E. Saji, Transport theory calculation for a heterogeneous multiassembly problem by characteristics method with direct neutron path linking technique, J. Nucl. Sci. Technol. 37 (2000) 1015.   DOI
14 K. Smith, J.D. Rhodes, Full-core, 2-D, LWR core calculations with CASMO-4E, in: Proc. PHYSOR, Seoul, South Korea, 2002 (CD-ROM).
15 A. Yamamoto, Generalized coarse-mesh Rebalance method for acceleration of neutron transport calculations, Nucl. Sci. Eng. 151 (2005) 274.   DOI
16 A. Yamamoto, K. Kirimura, Y. Kamiyama, K. Yamaji, S. Kosaka, H. Matsumoto, Angular dependent transmission probability method for fast reactor core transport analysis, Trans. Am. Nucl. Soc. 112 (2015) 736.
17 Z. Liu, K. Smith, B. Forget, A cumulative migration method for computing rigorous transport cross sections and diffusion coefficients for LWR lattices with Monte Carlo, in: Proc. PHYSOR2016, Sun Valley, ID, May 1-5, 2016 (USB drive).
18 Y.A. Chao, A new SPN theory formulation with self-consistent physical assumptions on angular flux, Ann. Nucl. Energy 87 (2016) 137.   DOI
19 Z. Weiss, G. Ball, Ray-tracing in complicated geometries, Ann. Nucl. Energy 18 (1991) 483.   DOI
20 Y.A. Chao, A. Yamamoto, The explicit representation for the angular flux solution in simplified PN (SPN) theory, in: Proc. PHYSOR2012, Knoxville, TN, Apr. 15-20, 2012 (CD-ROM).
21 R. Roy, Anisotropic scattering for integral transport codes: Part 2. Cyclic tracking and its application to XY lattices, Ann. Nucl. Energy 18 (1991) 511.   DOI
22 OECD/NEA, Benchmark on Deterministic Transport Calculations Without Spatial Homogenisation - MOX Fuel Assembly 3-D Extension Case, vol. 16, NEA/NSC/DOC(2005), 2005.
23 M. Jarrett, B. Kochunas, A. Zhu, T. Downar, Analysis of stabilization techniques for CMFD acceleration of neutron transport problems, Nucl. Sci. Eng. 184 (2016) 208.   DOI
24 E. Larsen, Infinite medium solutions to the transport equation, S_n discretization schemes, and the diffusion approximation, in: Proceedings of the Joint International Topical Meeting on Mathematics and Computation and Supercomputing in Nuclear Applications, Salt Lake City, UT, USA, 2001.
25 L. Li, A Low Order Acceleration Scheme for Solving the Neutron Transport Equation, Massachusetts Institute of Technology, Cambridge, MA, 2013.
26 S. Yuk, N.Z. Cho, Comparison of 1-D/1-D fusion method and 1-D/1-D hybrid method in two-dimensional neutron transport problems: convergence analysis and numerical results, Nucl. Sci. Eng. 184 (2016) 151.   DOI
27 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, in: Proc. PHYSOR 2004, Apr. 25-29, 2004 (CD-ROM).
28 R. Sanchez, Prospects in deterministic three-dimensional whole-core transport calculations, Nucl. Eng. Technol. 44 (2012) 113.   DOI
29 J.Y. Cho, H.G. Joo, K.S. Kim, S.Q. Zee, M.H. Chang, Three-dimensional heterogeneous whole core transport calculation employing planar MOC solutions, Trans. Am. Nucl. Soc. 87 (2002) 234.
30 S. Kosaka, T. Takeda, Verification of 3D heterogeneous core transport calculation utilizing non-linear iteration technique, J. Nucl. Sci. Technol. 41 (2004) 645-654.   DOI