Neutronic Design of Uranium-Plutonium Nitride Fuel-Based Gas-Cooled Fast Reactor (GFR)

This study presents the calculation results of the cell, and core Gas-cooled Fast Reactor (GFR) based fuel Uranium-Plutonium Nitride (U, Pu)N. Parameter survey results of calculations of the fuel cell consisting of a kinf, burnup level, and the conversion ratio and for the calculation of the reactor...

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Bibliographic Details
Main Authors: S. Novalianda, M. Ariani, F. Monado, Z. Su’ud
Format: Article
Published: Semarang State University 2018-11-01
Series:Jurnal Pendidikan Fisika Indonesia
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