Evaluation of fast fission factor in a typical pool type research reactor

One of the important factors of a nuclear reactor core is the fast fission factor.  This paper calculates this parameter based on space and energy-dependent method using the PTRAC card of MCNPX code. Tehran research reactor (TRR) is taken as a case study, and the parameter analyses are performed on...

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Bibliographic Details

Published in:	Journal of Nuclear Research and Applications
Main Authors:	M. Arkani, S. Khakshournia
Format:	Article
Language:	English
Published:	Nuclear Science and Technology Research Institute (NSTRI) 2022-01-01
Subjects:	fast fission factor mcnpx ptrac tehran research reactor
Online Access:	https://jonra.nstri.ir/article_1335_8b5af7f5c8f60066d1ed5e27b77f72a5.pdf