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


Unalan S.

FUSION TECHNOLOGY, vol.33, no.4, pp.398-417, 1998 (Journal Indexed in SCI) identifier identifier

  • Publication Type: Article / Article
  • Volume: 33 Issue: 4
  • Publication Date: 1998
  • Doi Number: 10.13182/fst98-a40
  • Title of Journal : FUSION TECHNOLOGY
  • Page Numbers: pp.398-417
  • Keywords: rejuvenation, material damage, blanket performance, BLANKETS, DRIVEN, FISSION, DESIGN

Abstract

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.