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Cited article:

The P_ij matrix and flux calculation of one-dimensional neutron transport in the slab geometry of nuclear fuel cell using collision probability method

Mohammad Ali Shafii, Jakaria Usman, Seni H. J. Tongkukut, Ade Gafar Abdullah

MATEC Web Conf., 197 (2018) 02006

Published online: 2018-09-12

DOI: https://doi.org/10.1051/matecconf/201819702006

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Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction

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Calculation of Collision Probability Matrix of Nuclear Fuel Cell as a Function of Neutron Energy Group Using Flat Flux Model

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International Journal of Mechanics 15 121 (2021)
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