Mehtap DÜZ, Hilal BARDAKCİ

7982

The Comparison of Effect on Neutronic Calculations of ENDF/B-VIII.0 Nuclear Library and Am-Cm Additive Fluids in a Hybrid Reactor System

The Comparison of Effect on Neutronic Calculations of ENDF/B-VIII.0 Nuclear Library and Am-Cm Additive Fluids in a Hybrid Reactor System

In this study, a fusion–fission hybrid reactor system was designed by using V4Cr4Ti Ferritic steel structural material and the molten salt-heavy metal mixture 79,9% Li17Pb83 + 20% ThF4 + 0,1% AmO2 and 79,9% Li17Pb83 + 20% ThF4 + 0,1% CmO2, as fluids. The fluids were used in the liquid first wall, blanket and shield zones of a fusion–fission hybrid reactor system. Beryllium (Be) zone with the width of 3 cm was used for the neutron multiplication between the liquid first wall and blanket. In this study was investigated the nuclear parameters such as tritium breeding ratio (TBR), energy multiplication factor (M), heat deposition rate, fission reaction rate in liquid first wall, blanket and shield zones. Three-dimensional analyses were performed by using the Monte Carlo code MCNPX-2.7.0, NJOY and ENDF/B-VIII.0 nuclear data library.

Keywords:

Nuclear Library Hybrid Reactor, Fluids,

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Journal of Physical Chemistry and Functional Materials-Cover

ISSN: 2651-3080
Yayın Aralığı: Yılda 2 Sayı
Başlangıç: 2018
Yayıncı: Niyazi BULUT

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Mehtap DÜZ, Hilal BARDAKCİ