Testing of uranium dioxide enriched with 233U under reducing conditions

Kaija Ollila, V. Oversby

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

Original languageEnglish
Title of host publicationProceedings of the 29th International Symposium on the Scientific Basis for Nuclear Waste Management XXIX
EditorsPierre Iseghem
PublisherMaterials Research Society
Pages441-448
ISBN (Print)1558998896, 9781558998896
DOIs
Publication statusPublished - 2006
MoE publication typeB3 Non-refereed article in conference proceedings
EventScientific basis for nuclear waste management XXIX - Ghent, Belgium
Duration: 12 Sep 200616 Sep 2006

Publication series

SeriesMaterials Research Society Symposia Proceedings
Number932
ISSN0272-9172

Conference

ConferenceScientific basis for nuclear waste management XXIX
CountryBelgium
CityGhent
Period12/09/0616/09/06

Cite this

Ollila, K., & Oversby, V. (2006). Testing of uranium dioxide enriched with 233U under reducing conditions. In P. Iseghem (Ed.), Proceedings of the 29th International Symposium on the Scientific Basis for Nuclear Waste Management XXIX (pp. 441-448). Materials Research Society. Materials Research Society Symposia Proceedings, No. 932 https://doi.org/10.1557/PROC-932-76.1