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Effects of fission product accumulation in cubic zirconia
dc.contributor.authorWang, L. M.en_US
dc.contributor.authorWang, S. X.en_US
dc.contributor.authorZhu, S.en_US
dc.contributor.authorEwing, Rodney C.en_US
dc.date.accessioned2011-11-15T16:03:57Z
dc.date.available2011-11-15T16:03:57Z
dc.date.issued2000-07-07en_US
dc.identifier.citationWang, L. M.; Wang, S. X.; Zhu, S.; Ewing, R. C. (2000). "Effects of fission product accumulation in cubic zirconia." AIP Conference Proceedings 532(1): 95-97. <http://hdl.handle.net/2027.42/87572>en_US
dc.identifier.otherAPCPCS-532-1en_US
dc.identifier.urihttps://hdl.handle.net/2027.42/87572
dc.description.abstractYttria stabilized cubic-zirconia (YSZ) is a promising candidate material for both inert matrix fuel and waste form based on its high solubility for actinides, high chemical durability and its reported exceptional stability under radiation. Because the incorporation of fission and other transmutation products during burnup may significantly affect the radiation response and the chemical durability of cubic zirconia, the solubility and mobility of the fission product nuclides in the inert matrix fuel at high temperatures (reactor fuel conditions) and low temperatures (repository conditions) are important. © 2000 American Institute of Physics.en_US
dc.publisherThe American Institute of Physicsen_US
dc.rights© The American Institute of Physicsen_US
dc.titleEffects of fission product accumulation in cubic zirconiaen_US
dc.typeArticleen_US
dc.subject.hlbsecondlevelPhysicsen_US
dc.subject.hlbtoplevelScienceen_US
dc.description.peerreviewedPeer Revieweden_US
dc.contributor.affiliationumUniversity of Michigan, Ann Arbor, Michigan 48109en_US
dc.description.bitstreamurlhttp://deepblue.lib.umich.edu/bitstream/2027.42/87572/2/95_1.pdf
dc.identifier.doi10.1063/1.1292216en_US
dc.identifier.sourcePLUTONIUM FUTURES - - THE SCIENCE: Topical Conference on Plutonium and Actinidesen_US
dc.owningcollnamePhysics, Department of


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