Coarse mesh finite difference acceleration of the random ray method

Choi, Sooyoung; Kochunas, Brendan

doi:10.1016/j.anucene.2024.110848

Title: Coarse mesh finite difference acceleration of the random ray method

Journal Article · 01 January 2025 · Annals of Nuclear Energy

DOI: https://doi.org/10.1016/j.anucene.2024.110848 · OSTI ID:2440123

; Kochunas, Brendan

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Sponsoring Organization:: USDOE

OSTI ID:: 2440123

Journal Information:: Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Journal Issue: C Vol. 210; ISSN 0306-4549

Publisher:: ElsevierCopyright Statement

Country of Publication:: United Kingdom

Language:: English

References (9)

Acceleration of source convergence in Monte Carlo k-eigenvalue problems via anchoring with a p-CMFD deterministic method Yun, Sunghwan; Cho, Nam Zin Annals of Nuclear Energy, Vol. 37, Issue 12 https://doi.org/10.1016/j.anucene.2010.07.018	journal	December 2010
An optimally diffusive Coarse Mesh Finite Difference method to accelerate neutron transport calculations Zhu, Ang; Jarrett, Michael; Xu, Yunlin Annals of Nuclear Energy, Vol. 95 https://doi.org/10.1016/j.anucene.2016.05.004	journal	September 2016
Performance evaluation of CMFD on inter-cycle correlation reduction of Monte Carlo simulation Park, Jinsu; Zhang, Peng; Lee, Hyunsuk Computer Physics Communications, Vol. 235 https://doi.org/10.1016/j.cpc.2018.09.014	journal	February 2019
The Random Ray Method for neutral particle transport Tramm, John R.; Smith, Kord S.; Forget, Benoit Journal of Computational Physics, Vol. 342 https://doi.org/10.1016/j.jcp.2017.04.038	journal	August 2017
Benchmark on deterministic 3-D MOX fuel assembly transport calculations without spatial homogenization Smith, M. A.; Lewis, E. E.; Na, Byung-Chan Progress in Nuclear Energy, Vol. 48, Issue 5 https://doi.org/10.1016/j.pnucene.2006.01.002	journal	July 2006
A Comparison of Stochastic mesh cell Volume Computation Strategies for the Random ray Method of Neutral Particle Transport Tramm, John R.; Siegel, Andrew R.; Lund, Amanda L. EPJ Web of Conferences, Vol. 247 https://doi.org/10.1051/epjconf/202124703021	journal	January 2021
A Consistent CMFD Formulation for the Acceleration of Neutron Transport Calculations Based on the Finite Element Method Jung, Yeon Sang; Yang, Won Sik Nuclear Science and Engineering, Vol. 185, Issue 2 https://doi.org/10.1080/00295639.2016.1272369	journal	February 2017
Acceleration and Real Variance Reduction in Continuous-Energy Monte Carlo Whole-Core Calculation via p-CMFD Feedback Jo, YuGwon; Cho, Nam Zin Nuclear Science and Engineering, Vol. 189, Issue 1, 26-40 https://doi.org/10.1080/00295639.2017.1373517	journal	October 2017
VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion Kochunas, Brendan; Collins, Benjamin; Stimpson, Shane Nuclear Science and Engineering, Vol. 185, Issue 1 https://doi.org/10.13182/NSE16-39	journal	January 2017

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