Potential of a catalyzed fusion-driven hybrid reactor for the regeneration of CANDU spent fuel

Journal Article · Thu Aug 01 04:00:00 EDT 1991 · Fusion Technology; (United States)

OSTI ID:5567963

Sahin, S ^[1]; Baltacioglu, E; Yapici, H ^[2]

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1. Gazi Univ., Teknik Egitim Fakueltesi, Besevler Ankara (TR)
2. Erciyes Univ., Muehendislik Fakueltesi, Kayseri (TR)

In this paper the potential of a catalyzed fusion-driven fast hybrid blanket to regenerate Canada deuterium uranium (CANDU) spent fuel is investigated. The investigations are done to achieve enrichment grades of fissile isotopes (EGFIs) in four applications: recycling in a conventional commercial CANDU reactor (EGFI = 0.71 to 0.9%); recycling in an advanced conceptual CANDU reactor with a high burnup rate (EGFI = 1%); recycling in an advanced breeder with thorium fuel (EGFI {gt} 1.5%); recycling in a conventional light water reactor (LWR) (EGFI {gt} 3%). The regeneration periods of 5 to 7, 6 to 9, 12 to 15 and {gt}30 months, respectively, are evaluated for the four reactor types under a first-wall fusion neutron current load of 10{sup 14} (14.1-MeV n)/cm{sup 2} {center dot} s, corresponding to 2.64 MW/m{sup 2} and a plant factor of 75%. During the regeneration process, the burnup rates vary from 2000 MWd/t (for conventional CANDU) to 10,000 MWd/t (for LWRs), so that multiple recycling becomes possible.

• OSTI ID: 5567963
• Journal Information: Fusion Technology; (United States), Journal Name: Fusion Technology; (United States) Vol. 20:1; ISSN 0748-1896; ISSN FUSTE
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDES
BREEDER REACTORS
BREEDING BLANKETS
CANDU TYPE REACTORS
DOUGLAS POINT ONTARIO REACTOR
ELEMENTS
ENERGY SOURCES
ENRICHMENT
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FIRST WALL
FUELS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
HYBRID REACTORS
MATERIALS
METALS
NATURAL URANIUM REACTORS
NUCLEAR FUELS
NUCLEAR REACTIONS
NUCLEOSYNTHESIS
PERFORMANCE TESTING
PHWR TYPE REACTORS
PRESSURE TUBE REACTORS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RECYCLING
RESEARCH AND TEST REACTORS
SPENT FUELS
SUBCRITICAL ASSEMBLIES
SYNTHESIS
TESTING
THERMAL REACTORS
THERMONUCLEAR REACTIONS
THERMONUCLEAR REACTOR WALLS
THORIUM