skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Conservation of migration area by transport cross sections using Cumulative Migration Method in deterministic heterogeneous reactor transport analysis

Abstract

Not provided.

Authors:
; ORCiD logo; ;
Publication Date:
Research Org.:
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1801259
DOE Contract Number:  
NE0008578
Resource Type:
Journal Article
Journal Name:
Progress in Nuclear Energy
Additional Journal Information:
Journal Volume: 127; Journal Issue: C; Journal ID: ISSN 0149-1970
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
Nuclear Science & Technology

Citation Formats

Liu, Zhaoyuan, Giudicelli, Guillaume, Smith, Kord, and Forget, Benoit. Conservation of migration area by transport cross sections using Cumulative Migration Method in deterministic heterogeneous reactor transport analysis. United States: N. p., 2020. Web. doi:10.1016/j.pnucene.2020.103447.
Liu, Zhaoyuan, Giudicelli, Guillaume, Smith, Kord, & Forget, Benoit. Conservation of migration area by transport cross sections using Cumulative Migration Method in deterministic heterogeneous reactor transport analysis. United States. https://doi.org/10.1016/j.pnucene.2020.103447
Liu, Zhaoyuan, Giudicelli, Guillaume, Smith, Kord, and Forget, Benoit. 2020. "Conservation of migration area by transport cross sections using Cumulative Migration Method in deterministic heterogeneous reactor transport analysis". United States. https://doi.org/10.1016/j.pnucene.2020.103447.
@article{osti_1801259,
title = {Conservation of migration area by transport cross sections using Cumulative Migration Method in deterministic heterogeneous reactor transport analysis},
author = {Liu, Zhaoyuan and Giudicelli, Guillaume and Smith, Kord and Forget, Benoit},
abstractNote = {Not provided.},
doi = {10.1016/j.pnucene.2020.103447},
url = {https://www.osti.gov/biblio/1801259}, journal = {Progress in Nuclear Energy},
issn = {0149-1970},
number = C,
volume = 127,
place = {United States},
year = {2020},
month = {9}
}

Works referenced in this record:

Multitable Treatments of Anisotropic Scattering in S N Multigroup Transport Calculations
journal, June 1967


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


On the use of the Serpent Monte Carlo code for few-group cross section generation
journal, June 2011


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


Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code
journal, October 2016


Generation of Few-Group Diffusion Theory Constants by Monte Carlo Code McCARD
journal, September 2012


Flux-Limited Diffusion Theory with Anisotropic Scattering
journal, April 1984


The OpenMC Monte Carlo particle transport code
journal, January 2013


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


Simplified Treatments of Anisotropic Scattering in LWR Core Calculations
journal, March 2008