The neutronic calculations for some fluids, libraries and structural materials in a hybrid reactor system

Gunay M.

KERNTECHNIK, cilt.80, sa.5, ss.449-453, 2015 (SCI-Expanded) identifier identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 80 Sayı: 5
  • Basım Tarihi: 2015
  • Doi Numarası: 10.3139/124.110530
  • Dergi Adı: KERNTECHNIK
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Sayfa Sayıları: ss.449-453
  • İnönü Üniversitesi Adresli: Evet

Özet

In the present investigation, a hybrid reactor system was designed by using 100% Flibe, 90% Flibe-10% ThF4, 90 % Flibe-10% UF4 fluids, ENDF/B-VII, JEFF-3.1, JENDL-4.0, ROSFOND, BROND-2.2, CENDL-3.1 evaluated nuclear data libraries and Ferritic Steel, 9Cr2WVTa, V4Cr4Ti, SiC structural materials. The fluids were used in the liquid first wall, liquid second wall (blanket) and shield zones of a fusion-fission hybrid reactor system. The nuclear parameters of a fusion-fission hybrid reactor such as tritium breeding ratio (TBR), energy multiplication factor (M), heat deposition rate were computed in liquid first wall, blanket and shield zones. Three-dimensional nucleonic calculations were performed using the most recent version MCNPX-2.7.0 the Monte Carlo code.