Assessment of the neutronic performance of some alternative fluids in a fusion-fission hybrid reactor by using Monte Carlo method

Gunay M.

ANNALS OF NUCLEAR ENERGY, cilt.60, ss.93-97, 2013 (SCI-Expanded) identifier identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 60
  • Basım Tarihi: 2013
  • Doi Numarası: 10.1016/j.anucene.2013.04.036
  • Dergi Adı: ANNALS OF NUCLEAR ENERGY
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Sayfa Sayıları: ss.93-97
  • İnönü Üniversitesi Adresli: Evet

Özet

In this study, a fusion-fission hybrid reactor system was designed by using 9Cr2WVFa Ferritic steel structural material and the molten salt-heavy metal mixtures 99-95% Li20Sn80-1-5% SFG-Pu, 99-95% Li20Sn80-1-5% SFG-PuF4, or 99-95% Li20Sn80-1-5% SFG-PuO2, as fluids. The fluids were used in the liquid first wall, blanket and shield zones of a fusion-fission hybrid reactor system. Beryllium (Be) zone with the width of 3 cm was used for neutron multiplication between the liquid first wall and blanket.