Progress on inert matrix fuels for minor actinide transmutation in fast reactor
Abstract
An extensive irradiation program has been devoted by CEA to the assessment of transmutation using minor actinide bearing inert support targets. A first irradiation experiment was performed in the fast neutron reactor Phenix, in parallel to other experiments carried out in the HFR and Siloe reactors, in order to assess the behavior under fast neutron flux of various materials intended as inert support matrix for transmutation targets. This experiment, which included the two steps MATINA 1 and MATINA 1A, was completed in 2004 and underwent complete post irradiation examinations (PIE) , whose results are presented in this paper. All the pure inert materials showed a satisfactory behavior under fast neutrons except Al{sub 2}O{sub 3} - which exhibits a swelling close to 11 vol. % after irradiation. In presence of UO{sub 2} fissile particles, MgAl{sub 2}O{sub 4} proved to be more stable in term of swelling as inert support than MgO and Al{sub 2}O{sub 3} matrices, under the same irradiation conditions. A second experiment ECRIX H in Phenix involving composite pellets with an MgO matrix and AmO{sub 2-x} particles was completed in 2006. The very first PIE results on ECRIX H are described in this paper. At the light of thesemore »
- Authors:
-
- CEA Cadarache, Nuclear Energy Direction, Saint-Paul les Durance Cedex 13108 (France)
- CEA Saclay, Nuclear Energy Direction, Gif sur Yvette, 91191 (France)
- Publication Date:
- Research Org.:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI Identifier:
- 20979516
- Resource Type:
- Conference
- Resource Relation:
- Conference: Advanced nuclear fuel cycles and systems (GLOBAL 2007), Boise - Idaho (United States), 9-13 Sep 2007; Other Information: Country of input: France; 14 refs; Related Information: In: Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems, 1873 pages.
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ACTINIDES; ALUMINIUM OXIDES; CEA; FAST NEUTRONS; FUEL PELLETS; HFR REACTOR; IRRADIATION; MAGNESIUM OXIDES; MATRIX MATERIALS; NEUTRON FLUX; NUCLEAR FUELS; OPTIMIZATION; PHENIX REACTOR; POST-IRRADIATION EXAMINATION; SILOE REACTOR; SWELLING; TARGETS; TRANSMUTATION; URANIUM DIOXIDE
Citation Formats
Bonnerot, Jean-Marc, Ferroud-Plattet, Marie-Pierre, Lamontagne, Jerome, Warin, Dominique, and Gosmain, Lionel. Progress on inert matrix fuels for minor actinide transmutation in fast reactor. United States: N. p., 2007.
Web.
Bonnerot, Jean-Marc, Ferroud-Plattet, Marie-Pierre, Lamontagne, Jerome, Warin, Dominique, & Gosmain, Lionel. Progress on inert matrix fuels for minor actinide transmutation in fast reactor. United States.
Bonnerot, Jean-Marc, Ferroud-Plattet, Marie-Pierre, Lamontagne, Jerome, Warin, Dominique, and Gosmain, Lionel. 2007.
"Progress on inert matrix fuels for minor actinide transmutation in fast reactor". United States.
@article{osti_20979516,
title = {Progress on inert matrix fuels for minor actinide transmutation in fast reactor},
author = {Bonnerot, Jean-Marc and Ferroud-Plattet, Marie-Pierre and Lamontagne, Jerome and Warin, Dominique and Gosmain, Lionel},
abstractNote = {An extensive irradiation program has been devoted by CEA to the assessment of transmutation using minor actinide bearing inert support targets. A first irradiation experiment was performed in the fast neutron reactor Phenix, in parallel to other experiments carried out in the HFR and Siloe reactors, in order to assess the behavior under fast neutron flux of various materials intended as inert support matrix for transmutation targets. This experiment, which included the two steps MATINA 1 and MATINA 1A, was completed in 2004 and underwent complete post irradiation examinations (PIE) , whose results are presented in this paper. All the pure inert materials showed a satisfactory behavior under fast neutrons except Al{sub 2}O{sub 3} - which exhibits a swelling close to 11 vol. % after irradiation. In presence of UO{sub 2} fissile particles, MgAl{sub 2}O{sub 4} proved to be more stable in term of swelling as inert support than MgO and Al{sub 2}O{sub 3} matrices, under the same irradiation conditions. A second experiment ECRIX H in Phenix involving composite pellets with an MgO matrix and AmO{sub 2-x} particles was completed in 2006. The very first PIE results on ECRIX H are described in this paper. At the light of these first experiments, a second phase dedicated to the design optimization of the target was initiated and three new irradiation experiments - MATINA 2-3, CAMIX COCHIX in Phenix and HELIOS in HFR - were started in 2006 and 2007. (authors)},
doi = {},
url = {https://www.osti.gov/biblio/20979516},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jul 01 00:00:00 EDT 2007},
month = {Sun Jul 01 00:00:00 EDT 2007}
}