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


Ubeyli M.

JOURNAL OF FUSION ENERGY, cilt.22, sa.1, ss.51-57, 2003 (SCI-Expanded) identifier identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 22 Sayı: 1
  • Basım Tarihi: 2003
  • Doi Numarası: 10.1023/b:jofe.0000021555.70423.f1
  • Dergi Adı: JOURNAL OF FUSION ENERGY
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Sayfa Sayıları: ss.51-57
  • Anahtar Kelimeler: fusion, hybrid reactor, tritium breeding, SPENT FUEL, REJUVENATION, BLANKET, PERFORMANCE, DEUTERIUM, BREEDERS, THORIUM, DESIGN
  • Gazi Üniversitesi Adresli: Hayır

Özet

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.