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Title: Full core 3D simulation of the BEAVRS benchmark with OpenMOC

Authors:
; ORCiD logo;
Publication Date:
Sponsoring Org.:
USDOE
OSTI Identifier:
1703414
Resource Type:
Publisher's Accepted Manuscript
Journal Name:
Annals of Nuclear Energy (Oxford)
Additional Journal Information:
Journal Name: Annals of Nuclear Energy (Oxford) Journal Volume: 134 Journal Issue: C; Journal ID: ISSN 0306-4549
Publisher:
Elsevier
Country of Publication:
United Kingdom
Language:
English

Citation Formats

Gunow, Geoffrey, Forget, Benoit, and Smith, Kord. Full core 3D simulation of the BEAVRS benchmark with OpenMOC. United Kingdom: N. p., 2019. Web. https://doi.org/10.1016/j.anucene.2019.05.050.
Gunow, Geoffrey, Forget, Benoit, & Smith, Kord. Full core 3D simulation of the BEAVRS benchmark with OpenMOC. United Kingdom. https://doi.org/10.1016/j.anucene.2019.05.050
Gunow, Geoffrey, Forget, Benoit, and Smith, Kord. Sun . "Full core 3D simulation of the BEAVRS benchmark with OpenMOC". United Kingdom. https://doi.org/10.1016/j.anucene.2019.05.050.
@article{osti_1703414,
title = {Full core 3D simulation of the BEAVRS benchmark with OpenMOC},
author = {Gunow, Geoffrey and Forget, Benoit and Smith, Kord},
abstractNote = {},
doi = {10.1016/j.anucene.2019.05.050},
journal = {Annals of Nuclear Energy (Oxford)},
number = C,
volume = 134,
place = {United Kingdom},
year = {2019},
month = {12}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
https://doi.org/10.1016/j.anucene.2019.05.050

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Works referenced in this record:

The OpenMOC method of characteristics neutral particle transport code
journal, June 2014


An analysis of condensation errors in multi-group cross section generation for fine-mesh neutron transport calculations
journal, February 2018


Stabilization of multi-group neutron transport with transport-corrected cross-sections
journal, April 2019


A new three-dimensional method of characteristics for the neutron transport calculation
journal, February 2011


Generalized equivalence methods for 3D multi-group neutron transport
journal, February 2018


A consistent 2D/1D approximation to the 3D neutron transport equation
journal, December 2015


Cumulative migration method for computing rigorous diffusion coefficients and transport cross sections from Monte Carlo
journal, February 2018


A new characteristics algorithm for 3D transport calculations
journal, January 2003


Transport Theory Calculation for a Heterogeneous Multi-Assembly Problem by Characteristics Method with Direct Neutron Path Linking Technique
journal, December 2000


A high-performance, portable implementation of the MPI message passing interface standard
journal, September 1996


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journal, August 1981

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