Rejuvenation of CANDU (Canada deuterium uranium) spent fuel in a hybrid blanket

Conference · Sun Jan 01 04:00:00 EST 1989 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6474588

Sahin, S ^[1]; Yapici, H ^[2]

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1. Gazi Univ. (Turkey)
2. Erciyes Univ. (Turkey)

The existing nuclear power plants can utilize only a small fraction of their fissile fuel. The possibility of the rejuvenation of spent nuclear fuel in a hybrid blanket is an attractive application field for early-generation fusion reactors. In the past, this option was investigated for light water reactor spent fuel. Little attention has been paid to the rejuvenation of spent Canada deuterium uranium (CANDU) fuel, although this type of rector has the lowest burnup rate per fuel mass, and consequently the highest ratio of spent-fuel mass/burnup. At present, there are many CANDU reactors in operation, and a substantial quantity of spent fuel is being stored without any clearly defined plans for future use. In this work, a hybrid blanket is investigated that contains CANDU spent fuel. The main objective is to study the rejuvenation behavior in a hybrid blanket coupled with substantial in situ electricity production. 12 refs., 2 figs., 1 tab.

• OSTI ID: 6474588
• Report Number(s): CONF-890604--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 59
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
A CODES
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ACTINIDES
ALPHA DECAY RADIOISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
BREEDING RATIO
CANDU TYPE REACTORS
COMPUTER CODES
CONVERSION RATIO
ELEMENTS
ENERGY SOURCES
EVEN-ODD NUCLEI
FIRST WALL
FUEL CANS
FUELS
HEAVY NUCLEI
HEAVY WATER MODERATED REACTORS
HYBRID REACTORS
HYDROGEN ISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPE RATIO
ISOTOPES
LIGHT NUCLEI
MATERIALS
METALS
MINUTES LIVING RADIOISOTOPES
MULTIPLICATION FACTORS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON TRANSPORT
NUCLEAR FUEL CONVERSION
NUCLEAR FUELS
NUCLEI
ODD-EVEN NUCLEI
PLUTONIUM 239
PLUTONIUM 241
PLUTONIUM ISOTOPES
PRESSURE TUBE REACTORS
RADIATION FLUX
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RECYCLING
SPENT FUELS
THERMAL REACTORS
THERMONUCLEAR FUELS
THERMONUCLEAR REACTOR WALLS
THORIUM
TRITIUM
URANIUM 235
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES