| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 8069647 | Annals of Nuclear Energy | 2014 | 5 Pages |
Abstract
The nuclear parameters of a fusion-fission hybrid reactor such as neutron flux, heating, fission reaction rate were investigated according to the mixture components, radial energy spectrum in the designed system. In this study, the effect of spent fuel-grade Pu content in the designed system on these nuclear parameters were calculated by using the three-dimensional Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.
Keywords
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Energy Engineering and Power Technology
Authors
Mehtap Günay, Hızır Kasap,