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Title: Generalized equivalence methods for 3D multi-group neutron transport

Authors:
ORCiD logo; ; ORCiD logo
Publication Date:
Sponsoring Org.:
USDOE
OSTI Identifier:
1549238
Grant/Contract Number:  
NE0008578
Resource Type:
Publisher's Accepted Manuscript
Journal Name:
Annals of Nuclear Energy
Additional Journal Information:
Journal Name: Annals of Nuclear Energy Journal Volume: 112 Journal Issue: C; Journal ID: ISSN 0306-4549
Publisher:
Elsevier
Country of Publication:
United Kingdom
Language:
English

Citation Formats

Giudicelli, Guillaume, Smith, Kord, and Forget, Benoit. Generalized equivalence methods for 3D multi-group neutron transport. United Kingdom: N. p., 2018. Web. doi:10.1016/j.anucene.2017.09.024.
Giudicelli, Guillaume, Smith, Kord, & Forget, Benoit. Generalized equivalence methods for 3D multi-group neutron transport. United Kingdom. https://doi.org/10.1016/j.anucene.2017.09.024
Giudicelli, Guillaume, Smith, Kord, and Forget, Benoit. Thu . "Generalized equivalence methods for 3D multi-group neutron transport". United Kingdom. https://doi.org/10.1016/j.anucene.2017.09.024.
@article{osti_1549238,
title = {Generalized equivalence methods for 3D multi-group neutron transport},
author = {Giudicelli, Guillaume and Smith, Kord and Forget, Benoit},
abstractNote = {},
doi = {10.1016/j.anucene.2017.09.024},
journal = {Annals of Nuclear Energy},
number = C,
volume = 112,
place = {United Kingdom},
year = {2018},
month = {2}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
https://doi.org/10.1016/j.anucene.2017.09.024

Citation Metrics:
Cited by: 17 works
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Works referenced in this record:

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


Analysis of correlations and their impact on convergence rates in Monte Carlo eigenvalue simulations
journal, June 2016


Derivation of Optimum Polar Angle Quadrature Set for the Method of Characteristics Based on Approximation Error for the Bickley Function
journal, February 2007

  • Yamamoto, Akio; Tabuchi, Masato; Sugimura, Naoki
  • Journal of Nuclear Science and Technology, Vol. 44, Issue 2
  • DOI: 10.1080/18811248.2007.9711266

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


Cell Homogenization Method for Pin-by-Pin Neutron Transport Calculations
journal, September 2011

  • Kozlowski, Tomasz; Xu, Yunlin; Downar, Thomas J.
  • Nuclear Science and Engineering, Vol. 169, Issue 1
  • DOI: 10.13182/NSE08-85

Assembly homogenization techniques for core calculations
journal, January 2009


A Consistent Technique for the Global Homogenization of a Pressurized Water Reactor Assembly
journal, December 1991

  • H├ębert, Alain; Benoist, Pierre
  • Nuclear Science and Engineering, Vol. 109, Issue 4
  • DOI: 10.13182/NSE109-360

A Nonlinear Space-Angle Multigrid Acceleration for the Method of Characteristics in Unstructured Meshes
journal, February 2007