Neutronic investigation of the application of certain plutonium-mixed fluids in a fusion-fission hybrid reactor
Küçük Resim Yok
Tarih
2014
Yazarlar
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
Pergamon-Elsevier Science Ltd
Erişim Hakkı
info:eu-repo/semantics/closedAccess
Özet
In this study, the fluids that were investigated were contained increased mole fractions of the mixtures molten salt 99-95% Li20Sn80 and, the heavy metals 1-5% SFG-Pu, SFG-PuF4, SFG-PuO2. The fluids were used in the liquid first wall, blanket and shield zones of the designed hybrid reactor system. Beryllium (Be) zone with the width of 3 cm was used for the neutron multiplicity between liquid first wall and blanket. Four centimeter thick 9Cr2WVTa ferritic steel was used as the structural material. 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. Crown Copyright (C) 2013 Published by Elsevier Ltd. All rights reserved.
Açıklama
Anahtar Kelimeler
Hybrid reactor, Neutron flux, Heating, MCNPX-2.7.0
Kaynak
Annals of Nuclear Energy
WoS Q Değeri
Q3
Scopus Q Değeri
Q1
Cilt
63
