Neutronics and thermal-hydraulics coupling analysis using the FLUENT code and RELAP5-3D code for a molten salt fast reactor

Publication Information

Title

Japanese:	Neutronics and thermal-hydraulics coupling analysis using the FLUENT code and RELAP5-3D code for a molten salt fast reactor
English:	Neutronics and thermal-hydraulics coupling analysis using the FLUENT code and RELAP5-3D code for a molten salt fast reactor

Author

Japanese:	望月弘保.
English:	Hiroyasu Mochizuki.

Language

English

Journal/Book name

Japanese:	Nuclear Engineering and Design
English:	Nuclear Engineering and Design

Volume, Number, Page

Vol. 368 pp. 1-15

Published date

Aug. 11, 2020

Publisher

Japanese:	Elsevier
English:	Elsevier

Conference name

Japanese:
English:

Conference site

Japanese:
English:

DOI