Investigation of the neutronic potential of moderated and fast (D,T) hybrid blankets for rejuvenation of CANDU spent fuel

Journal Article · Wed Nov 01 04:00:00 EST 1989 · Fusion Technology; (United States)

OSTI ID:5689244

Sahini, S ^[1]; Yapici, H ^[2]

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

This paper reports on potential of moderated and fast hybrid blankets investigated for the rejuvenation of CANDU spent fuel. The moderated hybrid blanket has revealed poor neutronic performance and is not suitable for CANDU spent-fuel rejuvenation. For fast-fissioning blankets, a rejuvenation period of up to 24 months is investigated by a plant factor of 75% under a first-wall (deuterium, tritium) fusion neutron current load of 10{sup 14} to 14 MeV {center dot} n/cm{sup 2} {center dot} s, corresponding to 2.25 MW/m{sup 2}.

• OSTI ID: 5689244
• Journal Information: Fusion Technology; (United States), Journal Name: Fusion Technology; (United States) Vol. 16:3; ISSN 0748-1896; ISSN FUSTE
• Country of Publication: United States
• Language: English

Related Subjects

050700 -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700450* -- Fusion Technology-- Blankets & Cooling Systems-- (1992-)
BREEDING BLANKETS
CANDU TYPE REACTORS
D-T REACTORS
ENERGY SOURCES
FIRST WALL
FUELS
FUNCTIONS
HEAVY WATER MODERATED REACTORS
HYBRID REACTORS
MATERIALS
NEUTRONIC DAMAGE FUNCTIONS
NUCLEAR FUELS
PRESSURE TUBE REACTORS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
SPENT FUELS
THERMAL REACTORS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS