The NILO-CMFD Method for Iteratively Solving Coupled Neutron Transport–Thermal Hydraulics Problems

Adamowicz, Nickolas J.; Manera, Annalisa; Larsen, Edward W.

doi:10.1080/00295639.2022.2112900

The NILO-CMFD Method for Iteratively Solving Coupled Neutron Transport–Thermal Hydraulics Problems

Journal Article · 01 November 2022 · Nuclear Science and Engineering

DOI:https://doi.org/10.1080/00295639.2022.2112900· OSTI ID:2424807

^[1]; Manera, Annalisa ^[1]; Larsen, Edward W. ^[1]

University of Michigan, Department of Nuclear Engineering and Radiological Sciences, Ann Arbor, Michigan 48109-2104

Not provided.

Research Organization:: Univ. of Michigan, Ann Arbor, MI (United States)

Sponsoring Organization:: USDOE

OSTI ID:: 2424807

Journal Information:: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 2 Vol. 197; ISSN 0029-5639

Publisher:: Taylor & Francis

Country of Publication:: United States

Language:: English

References (9)

The Relationship between the Coarse-Mesh Finite Difference and the Coarse-Mesh Diffusion Synthetic Acceleration Methods Larsen, Edward W.; Kelley, Blake W. Nuclear Science and Engineering, Vol. 178, Issue 1 https://doi.org/10.13182/NSE13-47	journal	September 2014
Development of high-fidelity neutron transport code STREAM Choi, Sooyoung; Kim, Wonkyeong; Choe, Jiwon Computer Physics Communications, Vol. 264 https://doi.org/10.1016/j.cpc.2021.107915	journal	July 2021
A Robust, Relaxation-Free Multiphysics Iteration Scheme for CMFD-Accelerated Neutron Transport k-Eigenvalue Calculations—II: Numerical Results Shen, Qicang; Choi, Sooyoung; Kochunas, Brendan Nuclear Science and Engineering, Vol. 195, Issue 11 https://doi.org/10.1080/00295639.2021.1906586	journal	June 2021
An assessment of coupling algorithms for nuclear reactor core physics simulations Hamilton, Steven; Berrill, Mark; Clarno, Kevin Journal of Computational Physics, Vol. 311 https://doi.org/10.1016/j.jcp.2016.02.012	journal	April 2016
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
Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers Jung, Yeon Sang; Shim, Cheon Bo; Lim, Chang Hyun Annals of Nuclear Energy, Vol. 62 https://doi.org/10.1016/j.anucene.2013.06.031	journal	December 2013
Fourier analysis of iteration schemes for k-eigenvalue transport problems with flux-dependent cross sections Kochunas, Brendan; Fitzgerald, Andrew; Larsen, Edward Journal of Computational Physics, Vol. 345 https://doi.org/10.1016/j.jcp.2017.05.028	journal	September 2017
A Robust, Relaxation–Free Multiphysics Iteration Scheme for CMFD–Accelerated Neutron Transport k–Eigenvalue Calculations–I: Theory Shen, Qicang; Kochunas, Brendan Nuclear Science and Engineering, Vol. 195, Issue 11 https://doi.org/10.1080/00295639.2021.1906585	journal	June 2021
Low-order multiphysics coupling techniques for nuclear reactor applications Walker, Erik D.; Collins, Benjamin; Gehin, Jess C. Annals of Nuclear Energy, Vol. 132 https://doi.org/10.1016/j.anucene.2019.04.022	journal	October 2019

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