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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| Asıl Yazarlar: | , , , |
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| Materyal Türü: | Kitap |
| Baskı/Yayın Bilgisi: |
Semarang State University,
2018-11-01T00:00:00Z.
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| Yer Numarası: |
A1234.567 |
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| Kopya Bilgisi 1 | Kütüphanede |