Rejuvenation of the CANDU spent fuel in (D-T)-driven hybrid reactors

Unalan S.

FUSION TECHNOLOGY, cilt.33, sa.4, ss.398-417, 1998 (SCI-Expanded) identifier identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 33 Sayı: 4
  • Basım Tarihi: 1998
  • Doi Numarası: 10.13182/fst98-a40
  • Dergi Adı: FUSION TECHNOLOGY
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Sayfa Sayıları: ss.398-417
  • Anahtar Kelimeler: rejuvenation, material damage, blanket performance, BLANKETS, DRIVEN, FISSION, DESIGN
  • Erciyes Üniversitesi Adresli: Evet

Özet

The possibility of Canada deuterium uranium reactor (CANDU) spent-fuel rejuvenation in deuterium-tritium (D-T)-driven hybrid reactors having 17.8 cm of fissile zone thickness is investigated for various plasma chamber dimensions (DR = 18.7, 118.7 218.7, and 418.7 cm) with a linear fusion neutron source (plasma dimension is assumed as DR/2) under different first-wall loads (P-w = 2, 4, 6, 8, and 10 MW/m(2)). The behavior of the spent fuel is observed during 36 months for discrete time intervals of Delta t = 15 days and by a plant factor of 75%. The fissile fuel zone is consider-ed to be cooled with three different coolants: gas (He or CO2), Flibe (Li2BEF4), and natural Li.