EPJ Web Conf.
Volume 154, 20173rd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT 2017)
|Number of page(s)||3|
|Published online||29 September 2017|
The calculation of neutron flux using Monte Carlo method
İnönü University, Science and Art Faculty, Physics Department, Malatya, Turkey
* Corresponding author: email@example.com
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
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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