Irradiation experiments and fabrication technology of inert matrix fuels for the transmutation of actinides

Conference · Wed Sep 15 00:00:00 EDT 1999

OSTI ID:23142193

Schram, R. P.C.; Bakker, K.; Boshoven, J. G.; Dassel, G.; Hein, H.; Van der Laan, R. R.; Neeft, E. A.C. ^[1]; Konings, R. J.M. ^[2]; Conrad, R. ^[3]

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1. NRG Petten, P.O.Box 25, 1755 ZG Petten (Netherlands)
2. European Commission, Institute for Transuranium Elements, Postfach 2340, 76125 Karlsruhe (Germany)
3. European Commission, Institute for Advanced Materials, P.O. Box2, 1755 ZG Petten (Netherlands)

Inert matrix fuels offer an interesting opportunity for the reduction of the radiotoxicity of nuclear waste. The irradiation stability of various inert matrices are presently under investigation. In the EFFTRA T3 experiment the following inert matrices were irradiated: CeO{sub 2}, Y{sub 2}O{sub 3}, MgO, MgAl{sub 2}O{sub 4} (spinel), and Y{sub 3}Al{sub 5}O{sub 12}. The inert matrices were irradiated with and without fissile material, such that the irradiation damage associated with fission can be determined. The preliminary results of the post-irradiation examinations, which are ongoing, are presented.

• Research Organization: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 23142193
• Resource Relation: Conference: Global'99: International Conference on Future Nuclear Systems - Nuclear Technology - Bridging the Millennia, Las Vegas, NV (United States), 29 Aug - 3 Sep 1999; Other Information: Country of input: France; 3 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
ACTINIDES
CERIUM OXIDES
FABRICATION
FISSILE MATERIALS
FISSION
IRRADIATION
MAGNESIUM OXIDES
MATRICES
NUCLEAR FUELS
POST-IRRADIATION EXAMINATION
RADIOACTIVE WASTES
TRANSMUTATION
YTTRIUM OXIDES