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

Fusion Technology

Volumn 33, Issue 4, 1998, Pages 398-417

  Ünalan, Sebahattin ^a  

^a ERCIYES UNIVERSITY   (Turkey)

Author keywords

Blanket performance; Material damage; Rejuvenation

Indexed keywords

BREEDER REACTORS; CALCULATIONS; COOLANTS; DEUTERIUM; FISSION PRODUCTS; NEUTRON SOURCES; PERFORMANCE; PLASMA DENSITY; SPENT FUELS; TEMPERATURE; TRITIUM;

CUMULATIVE FISSILE FUEL ENRICHMENT; HYBRID BLANKET; HYBRID REACTORS; NEUTRON FLUX; PLASMA CHAMBER DIMENSION; SPENT FUEL REJUVENATION;

BREEDING BLANKETS;

EID: 0032114998     PISSN: 07481896     EISSN: None     Source Type: Journal    
DOI: 10.13182/FST98-A40     Document Type: Article

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