2017
DOI: 10.1051/epjconf/201715306019
|View full text |Cite
|
Sign up to set email alerts
|

CAD-Based Monte Carlo Neutron Transport KSTAR Analysis for KSTAR

Abstract: Abstract. The Monte Carlo (MC) neutron transport analysis for a complex nuclear system such as fusion facility may require accurate modeling of its complicated geometry. In order to take advantage of modeling capability of the computer aided design (CAD) system for the MC neutronics analysis, the Seoul National University MC code, McCARD, has been augmented with a CAD-based geometry processing module by imbedding the OpenCASCADE CAD kernel. In the developed module, the CAD geometry data are internally converte… Show more

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...

Citation Types

0
0
0

Publication Types

Select...

Relationship

0
0

Authors

Journals

citations
Cited by 0 publications
references
References 9 publications
0
0
0
Order By: Relevance

No citations

Set email alert for when this publication receives citations?