Analysis of Kobayashi benchmark with indigenous Monte Carlo neutron transport code PATMOC

The solution of the neutron transport equation is the basic input for the reactor physics design of a nuclear reactor system. Because of the complexities of geometry and cross-section data, the neutron transport equation is generally solved using numerical methods. One of the difficulties in the sol...

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Bibliographic Details
Main Authors: Amod Kishore Mallick, Umasankari Kannan
Format: Article
Language:English
Published: Elsevier 2023-12-01
Series:Physics Open
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S2666032623000443