On the tritium breeding capability of Flibe, Flinabe, and Li20Sn80 in a fusion-fission (hybrid) reactor

Ubeyli M.

JOURNAL OF FUSION ENERGY, vol.22, no.1, pp.51-57, 2003 (SCI-Expanded) identifier identifier

  • Publication Type: Article / Article
  • Volume: 22 Issue: 1
  • Publication Date: 2003
  • Doi Number: 10.1023/b:jofe.0000021555.70423.f1
  • Journal Name: JOURNAL OF FUSION ENERGY
  • Journal Indexes: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Page Numbers: pp.51-57
  • Keywords: fusion, hybrid reactor, tritium breeding, SPENT FUEL, REJUVENATION, BLANKET, PERFORMANCE, DEUTERIUM, BREEDERS, THORIUM, DESIGN
  • Gazi University Affiliated: No

Abstract

In a commercial (DT) driven fusion reactor, the tritium breeding ratio per incident fusion neutron must be greater than 1.05 to maintain tritium self-sufficiency for the driver. In this study tritium breeding capability of three different coolants, namely Flibe (LiF.BeF2), Flinabe (LiF.NaF.BeF2), and Li20Sn80 in a (DT) driven fusion-fission (hybrid) reactor was investigated for different refractory alloys (W-5Re, TZM, T111, and Nb-1Zr) as structural material. Neutron transport calculations were conducted with the help of SCALE 4.3 SYSTEM by solving the Boltzmann transport equation with code XSDRNPM. The contribution of Flibe, Flinabe, and Li20Sn80 with respect to Li-6 enrichment in their lithium content to overall TBR was investigated. In addition, the effect of structural material type on TBR was examined.