Modeling and neutronic analysis of pin-cell comprising...

Annals of Nuclear Energy 2021 / 02 Vol. 151

Modeling and neutronic analysis of pin-cell comprising nuclear fuel with different chemical composition and neutron moderator using Monte Carlo code OpenMC

Reza, Farshid, Sahadath, Md. Hossain, Akter, Yasmin
How much do you like this book?
What’s the quality of the file?
Download the book for quality assessment
What’s the quality of the downloaded files?
Volume:
151
Journal:
Annals of Nuclear Energy
DOI:
10.1016/j.anucene.2020.107946
Date:
February, 2021
File:
PDF, 1.96 MB
2021
Conversion to is in progress
Conversion to is failed