| Issue |
EPJ Web Conf.
Volume 154, 2017
3rd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT 2017)
|
|
|---|---|---|
| Article Number | 01025 | |
| Number of page(s) | 3 | |
| DOI | https://doi.org/10.1051/epjconf/201715401025 | |
| Published online | 29 September 2017 | |
https://doi.org/10.1051/epjconf/201715401025
The calculation of neutron flux using Monte Carlo method
İnönü University, Science and Art Faculty, Physics Department, Malatya, Turkey
* Corresponding author: mehtap.gunay@inonu.edu.tr
Published online: 29 September 2017
In this study, a hybrid reactor system was designed by using 99–95% Li20Sn80 + 1-5% RG-Pu, 99–95% Li20Sn80 + 1-5% RG-PuF4, and 99–95% Li20Sn80 + 1-5% RG-PuO2 fluids, ENDF/B-VII.0 evaluated nuclear data library and 9Cr2WVTa structural material. The fluids were used in the liquid first wall, liquid second wall (blanket) and shield zones of a fusion–fission hybrid reactor system. The neutron flux was calculated according to the mixture components, radial, energy spectrum in the designed hybrid reactor system for the selected fluids, library and structural material. Three-dimensional nucleonic calculations were performed using the most recent version MCNPX-2.7.0 the Monte Carlo code.
© The Authors, published by EDP Sciences, 2017
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