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...
| Main Authors: | , , , |
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| Format: | Article |
| Language: | English |
| Published: |
Semarang State University
2018-11-01
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| Series: | Jurnal Pendidikan Fisika Indonesia |
| Subjects: | |
| Online Access: | https://journal.unnes.ac.id/nju/index.php/JPFI/article/view/6602 |