Direct Comparison of High-Order/Low-Order Transient Methods on the 2D-LRA Benchmark Problem

Kreher, Miriam A.; Smith, Kord; Forget, Benoit

doi:10.1080/00295639.2021.1980363

Direct Comparison of High-Order/Low-Order Transient Methods on the 2D-LRA Benchmark Problem

Journal Article · 21 December 2021 · Nuclear Science and Engineering

DOI:https://doi.org/10.1080/00295639.2021.1980363· OSTI ID:1979196

^[1]; Smith, Kord ^[1]; Forget, Benoit ^[1]

Massachusetts Institute of Technology, Nuclear Science & Engineering, Cambridge, Massachusetts

Not provided.

Research Organization:: Krell Institute, Ames, IA (United States)

Sponsoring Organization:: USDOE Office of Science (SC)

DOE Contract Number:: FG02-97ER25308

OSTI ID:: 1979196

Journal Information:: Nuclear Science and Engineering, Vol. 196, Issue 4; ISSN 0029-5639

Publisher:: Taylor & Francis

Country of Publication:: United States

Language:: English

References (9)

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Two-Level Coarse Mesh Finite Difference Formulation with Multigroup Source Expansion Nodal Kernels Yoon, Joo Il; Joo, Han Gyu Journal of Nuclear Science and Technology, Vol. 45, Issue 7 https://doi.org/10.1080/18811248.2008.9711467	journal	July 2008
Whole-core forward-adjoint neutron transport solutions with coupled 2-D MOC and 1-D SN and kinetics parameter calculation Wu, Qu; Peng, Xingjie; Tang, Xiao Progress in Nuclear Energy, Vol. 108 https://doi.org/10.1016/j.pnucene.2018.06.006	journal	September 2018
Some Numerical Experiments Concerning Space-Time Reactor Kinetics Behavior Yasinsky, J. B.; Henry, A. F. Nuclear Science and Engineering, Vol. 22, Issue 2 https://doi.org/10.13182/NSE65-A20236	journal	June 1965
Multiphysics reactor-core simulations using the improved quasi-static method Prince, Zachary M.; Ragusa, Jean C. Annals of Nuclear Energy, Vol. 125 https://doi.org/10.1016/j.anucene.2018.10.056	journal	March 2019
A New Scaling and Squaring Algorithm for the Matrix Exponential Al-Mohy, Awad H.; Higham, Nicholas J. SIAM Journal on Matrix Analysis and Applications, Vol. 31, Issue 3 https://doi.org/10.1137/09074721X	journal	January 2010
A Rayleigh quotient method for criticality eigenvalue problems in neutron transport Ortega, M. I.; Slaybaugh, R. N.; Brown, P. N. Annals of Nuclear Energy, Vol. 138 https://doi.org/10.1016/j.anucene.2019.107120	journal	April 2020
Quasistatic Treatment of Spatial Phenomena in Reactor Dynamics Ott, Karl Nuclear Science and Engineering, Vol. 26, Issue 4 https://doi.org/10.13182/NSE66-A18428	journal	December 1966
Diffusion theory methods for spatial kinetics calculations Sutton, T. M.; Aviles, B. N. Progress in Nuclear Energy, Vol. 30, Issue 2 https://doi.org/10.1016/0149-1970(95)00082-U	journal	January 1996

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