Monte Carlo calculations of the nuclear effects of certain fluids in a hybrid reactor
Küçük Resim Yok
Tarih
2016
Yazarlar
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
Pergamon-Elsevier Science Ltd
Erişim Hakkı
info:eu-repo/semantics/closedAccess
Özet
This study analyzes the effects of certain heavy-metal-salt fluids on nuclear parameters in a fusion-fission hybrid reactor. Calculated parameters include the tritium breeding ratio (TBR), energy multiplication factor (M), heat deposition rate, fission reaction rate, and fissile fuel breeding in the reactor's liquid first wall, blanket, and shield zones; gas production rates in the structural material of the reactor were calculated, as well. The fluid mixtures consisted of 93-85% Li20Sn50 + 5% SFG-PuO2 and 2-10% UO2, 93-85% Li20Sn80 + 5% SFG-PuO2 and 2-10% NpO2, and 93-85% Li20Sn50 + 5% SFG-PuO2 and 2-10% UCO. The fluids were used in the liquid first wall, blanket, and shield zones of a fusion fission hybrid reactor system. A 3 cm wide beryllium (Be) zone was used for neutron multiplier between the liquid first wall and the blanket. The structural material used was 9Cr2WVTa ferritic steel, measuring 4 cm in width. Three-dimensional analyses were performed using the Monte Carlo code MCNPX-2.7.0 and the ENDF/B-VILO nuclear data library. (C) 2015 Elsevier Ltd. All rights reserved.
Açıklama
Anahtar Kelimeler
TBR, M, Heat deposition rate, Fissile fuel breeding, Radiation damage, MCNPX-2.7.0
Kaynak
Progress in Nuclear Energy
WoS Q Değeri
Q2
Scopus Q Değeri
Q2
Cilt
86
