The calculation of neutron flux using Monte Carlo method

Autor: Günay Mehtap, Bardakçı Hilal
Jazyk: angličtina
Rok vydání: 2017
Předmět:
Zdroj: EPJ Web of Conferences, Vol 154, p 01025 (2017)
Druh dokumentu: article
ISSN: 2100-014X
DOI: 10.1051/epjconf/201715401025
Popis: 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.
Databáze: Directory of Open Access Journals