Monte Carlo analysis of LWR spent fuel transmutation in a fusion-fission hybrid reactor system

Sahin S., Sahin H. M., Tunc G.

NUCLEAR ENGINEERING AND TECHNOLOGY, cilt.50, sa.8, ss.1339-1348, 2018 (SCI-Expanded) identifier identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 50 Sayı: 8
  • Basım Tarihi: 2018
  • Doi Numarası: 10.1016/j.net.2018.08.006
  • Dergi Adı: NUCLEAR ENGINEERING AND TECHNOLOGY
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Sayfa Sayıları: ss.1339-1348
  • Anahtar Kelimeler: LWR spent fuel, Thorium, Time dependent neutronic analysis, Fusion-fission hybrid reactor, BED NUCLEAR-REACTOR, GRADE PLUTONIUM, NEUTRONIC ANALYSIS, CONCEPTUAL DESIGN, CODE SYSTEM, BURN-UP, THORIUM, REJUVENATION, MYRRHA, CRITICALITY
  • Gazi Üniversitesi Adresli: Evet

Özet

The aim of this paper is to determine neutronic performances of the light water reactor (LWR) spent fuel mixed with fertile thorium fuel in a FFHR. Time dependent three dimensional calculations for major technical data, such as blanket energy multiplication, tritium breeding ratio, cumulative fissile fuel enrichment and burnup have been performed by using Monte Carlo Neutron-Particle Transport code MCNPS 1.4, coupled with a novel interface code MCNPAS, which is developed by our research group. A self-sustaining tritium breeding ratio (TBR>1.05) has been kept throughout the calculations. The study has shown that the fissile fuel quality will be improved in the course of the transmutation of the LWR spent in the FFHR. The latter has gained the reusable fuel enrichment level conventional LWRs between one and two years. Furthermore, LWR spent fuel - thorium mixture provides higher burn-up values than in light water reactors. (C) 2018 Korean Nuclear Society, Published by Elsevier Korea LLC.