Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis

Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis

Multigroup cross section (MG XS) generation by the UNIST in-house Monte Carlo (MC) code MCS for fast reactor analysis using nodal diffusion codes is reported. The feasibility of the approach is quantified for two sodium fast reactors (SFRs) specified in the OECD/NEA SFR benchmark: a 1000 MWth metal-...

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Bibliographic Details
Main Authors: Tung Dong Cao Nguyen, Hyunsuk Lee, Deokjung Lee
Format: Article
Language:English
Published: Elsevier 2021-09-01
Series:Nuclear Engineering and Technology
Subjects:
Monte Carlo
Nodal diffusion
Multigroup
Cross section generation
SFR
MCS
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573321001479

Internet

http://www.sciencedirect.com/science/article/pii/S1738573321001479

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