Monte Carlo calculations of the nuclear effects of certain fluids in a hybrid reactor


Gunay M.

PROGRESS IN NUCLEAR ENERGY, cilt.86, ss.103-109, 2016 (SCI İndekslerine Giren Dergi) identifier identifier

  • Cilt numarası: 86
  • Basım Tarihi: 2016
  • Doi Numarası: 10.1016/j.pnucene.2015.10.017
  • Dergi Adı: PROGRESS IN NUCLEAR ENERGY
  • Sayfa Sayıları: ss.103-109

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.