Applicability of the Krško nuclear power plant core Monte Carlo model for the determination of the neutron source term

A detailed geometrical model of a Krško reactor core was developed using a Monte Carlo neutron transport code MCNP. The main goal of developing an MCNP core model is for it to be used in future research focused on ex-core calculations. A script called McCord was developed to generate MCNP input for...

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Bibliographic Details

Published in:	Nuclear Engineering and Technology
Main Authors:	Tanja Goričanec, Žiga Štancar, Domen Kotnik, Luka Snoj, Marjan Kromar
Format:	Article
Language:	English
Published:	Elsevier 2021-11-01
Subjects:	Pressurized water reactor Krško nuclear power plant Monte Carlo neutron transport MCNP CORD-2 In-core neutron detector
Online Access:	http://www.sciencedirect.com/science/article/pii/S1738573321002886