Journal of Nuclear Materials
Volume 373, Issues 1-3, 15 February 2008, Pages 186-189
UO2 oxidation site densities determined by one- and two-electron oxidants
Mohammad Mohsin Hossain and Mats Jonsson
- DOI:
http://dx.doi.org/10.1016/j.jnucmat.2007.05.042
2.
Journal of Nuclear Materials
Volume 372, Issues 2-3, 31 January 2008, Pages 215-225
Volatile fission product behaviour during thermal annealing of irradiated UO2 fuel oxidised up to U3O8
J.-P. Hiernaut, T. Wiss, D. Papaioannou, R.J.M. Konings and V.V. Rondinella
- DOI:
http://dx.doi.org/10.1016/j.jnucmat.2007.03.174
3.
Journal of Physics and Chemistry of Solids
Volume 66, Issues 2-4, February-April 2005, Pages 671-674
Proceedings of the 11th International Conference on High Temperature Materials Chemistry (HTMC-XI)
Remote fabrication and irradiation test of recycled nuclear fuel prepared by the oxidation and reduction of spent oxide fuel
Ho Jin Ryu, Kee Chan Song, Geun Il Park, Jung Won Lee and Myung Seung Yang
- DOI:
http://dx.doi.org/10.1016/j.jpcs.2004.06.080
4.
Journal of Molecular Catalysis A: Chemical
Volume 245, Issues 1-2, 15 February 2006, Pages 62-68
Effects of precursor and support variation in the performance of uranium oxide catalysts for CO oxidation and selective reduction of NO
Tom Campbel, Mark A. Newton, Vicky Boyd, Darren F. Lee and John Evans
- DOI:
http://dx.doi.org/10.1016/j.molcata.2005.09.030
5.
Surface and Coatings Technology
Volumes 158-159, September 2002, Pages 473-476
Proceedings of the 12th International Conference on SMMIB
Zirconium surface modification under fission product irradiation. Application to nuclear fuel cladding tubes
N Bérerd, H Catalette, A Chevarier, N Chevarier, H Faust and N Moncoffre
- DOI:
http://dx.doi.org/10.1016/S0257-8972(02)00290-6
