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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| Main Authors: | , , , |
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| Format: | Book |
| Published: |
Semarang State University,
2018-11-01T00:00:00Z.
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| Online Access: | Connect to this object online. |
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