689
Views
2
CrossRef citations to date
0
Altmetric
ARTICLE

Transport consistent diffusion coefficient for CMFD acceleration and comparison of convergence properties

ORCID Icon, ORCID Icon &
Pages 716-723 | Received 11 Mar 2019, Accepted 09 May 2019, Published online: 21 May 2019

References

  • Smith K. Nodal method storage reduction by non-linear iteration. Trans Am Nucl Soc. 1983;44:265–266.
  • Smith K, Rhodes JD Full-core, 2-D, LWR core calculations with CASMO-4E. Proc. PHYSOR2002; 2002 Oct 7–10; Seoul (South Korea). [CD-ROM].
  • Joo HG, Cho JY, Kim KS, et al. Methods and performance of a three-dimensional whole-core transport code DeCART. Proc. PHYSOR2004; 2004 Apr 25–29; Chicago Illinois (US). [CD-ROM].
  • Yamamoto A. Generalized coarse mesh rebalance method for acceleration of neutron transport calculations. Nucl Sci Eng. 2005;151:274–282.
  • Yamamoto A, Endo T, Tabuchi M, et al. An advanced lattice physics code for light water reactor analyses. Nucl Eng Technol. 2010;42:500–519.
  • Jung YS, Shim CB, Lim CH, et al. Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers. Ann Nucl Energy. 2013;62:357–374.
  • Boyd W, Shaner W, Li L, et al. The openMOC method of characteristics neutral particle transport code. Ann Nucl Energy. 2014;68:43–52.
  • Zhu A, Transient methods for pin-resolved whole core transport using the 2D-1D methodology in MPACT. Proc. M&C2015; 2015 Apr 19–23; Nashville Tennessee (US). [USB-DRIVE].
  • Chen J, Liu Z, Zhao C, et al. A new high-fidelity neutronics code NECP-X. Ann Nucl Energy. 2018;116:417–428.
  • Jarrett M, Kochunas B, Zhu A, et al. Analysis of stabilization techniques for CMFD acceleration of neutron transport problems. Nucl Sci Eng. 2016;184:208–227.
  • Larsen E Infinite medium solutions to the transport equation, Sn discretization schemes, and the diffusion approximation. Proc. of the Joint International Topical Meeting on Mathematics and Computation and Supercomputing in Nuclear Applications; 2001 Sep 9–13; Salt Lake City, UT, (USA). [CD-ROM].
  • Cho NZ, Lee GS, Park CJ. Partial current-based CMFD acceleration of the 2D/1D fusion method for 3D whole-core transport calculations. Trans Am Nucl Soc. 2003;88:594–596.
  • Yamamoto A, Giho A, Endo T. Recent developments in the GENESIS code based on the Legendre polynomial expansion of angular flux method. Nucl Eng Technol. 2017;49:1143–1156.
  • Cefus GR, Larsen EW. Stability analysis of the coarse-mesh rebalance. Nucl Sci Eng. 1990;105:31–39.
  • Hong SG, Kim KS, Song JS. Fourier convergence analysis of the rebalance methods for discrete ordinates transport equations in eigenvalue problems. Nucl Sci Eng. 2010;164:33–52.
  • Kim HT, Kim Y. Convergence studies on nonlinear coarse-mesh finite difference accelerations for neutron transport analysis. Nucl Sci Eng. 2018;191:136–149.
  • Benchmark on Deterministic Transport calculations without spatial homogenisation—MOX fuel assembly 3-d extension case. NEA/NSC/DOC(2005)16. 2005. Organisation for Economic Co-operation and Development/Nuclear Energy Agency.
  • Yamamoto A, Giho A, Kato Y, et al. - a three-dimensional heterogeneous transport solver based on the Legendre polynomial expansion of angular flux method. Nucl Sci Eng. 2017;186:1–22.

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.