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HIPed tailored ceramic waste forms for the immobilization of Cs, Sr and Tc

dc.contributor.authorCarter, MLen_AU
dc.contributor.authorStewart, MWAen_AU
dc.contributor.authorVance, ERen_AU
dc.contributor.authorBegg, BDen_AU
dc.contributor.authorMoricca, SAen_AU
dc.contributor.authorTripp, Jen_AU
dc.date.accessioned2026-06-04T06:27:20Zen_AU
dc.date.issued2007-12-01en_AU
dc.date.statistics2026-06-04en_AU
dc.descriptionPhysical copy of CD-Rom held by ANSTO Library at DDC: 621.48335/108en_AU
dc.description.abstractThe Advanced Fuel Cycle Initiative is developing advanced technologies to allow for the safe and economical disposal of waste from nuclear reactors. An important element of this initiative is the separation of key radionuclides. One of the systems being developed to separate key radionuclides is the UREX+1 process. The Tc and Cs/Sr solutions from UREX+1 process will require treatment and solidification for managed storage. This paper illustrates the benefits of HIPed tailored ceramic waste forms, to provide for the immobilization of separated Cs, Sr and Tc. Experimental data are presented for a Cs and Sr-bearing hollandite-rich tailored ceramic prepared with 12 wt% waste (on an oxide basis). Normalized MCC-1 type leach testing at 90°C for 28 days revealed extremely low Cs and Sr release rates of 0.003 and 0.004 g/m2/day respectively. Experimental data on the immobilization of Tc in titanate ceramics containing up to 40wt% TcO2 are also be presented. © American Nuclear Societyen_AU
dc.identifier.booktitleGLOBAL 2007: Advanced Nuclear Fuel Cycles and Systemsen_AU
dc.identifier.citationCarter, M., Stewart, M., Vance, E., Begg, B. D., Moricca, S., & Tripp, J. (2007). HIPed tailored ceramic waste forms for the immobilization of Cs, Sr and Tc. Paper presented to GLOBAL 2007 - 7th International Conference on Advanced Nuclear Fuel Cycles and Systems. In GLOBAL 2007 : advanced nuclear fuel cycles and systems, September 9-13, 2007, Boise, Idaho, (Vol. 3, pp. 1022-1028). Westmont, Illinois : American Nuclear Society.en_AU
dc.identifier.conferenceenddate2007-09-13en_AU
dc.identifier.conferencenameGLOBAL 2007 - 7th International Conference on Advanced Nuclear Fuel Cycles and Systemsen_AU
dc.identifier.conferenceplaceBoise, Idaho, USAen_AU
dc.identifier.conferencestartdate2007-09-09en_AU
dc.identifier.isbn9780894480553en_AU
dc.identifier.isbn0894480553en_AU
dc.identifier.pagination1022-1028en_AU
dc.identifier.urihttps://apo.ansto.gov.au/handle/10238/17242en_AU
dc.language.isoenen_AU
dc.publisherAmerican Nuclear Societyen_AU
dc.subjectCeramicsen_AU
dc.subjectSynthetic rocksen_AU
dc.subjectHigh-level radioactive wastesen_AU
dc.subjectCesiumen_AU
dc.subjectTechnetiumen_AU
dc.subjectStrontiumen_AU
dc.subjectFuel cycleen_AU
dc.subjectRadionuclide administrationen_AU
dc.subjectSeparation processesen_AU
dc.subjectWaste storageen_AU
dc.subjectActinidesen_AU
dc.subjectLeachingen_AU
dc.titleHIPed tailored ceramic waste forms for the immobilization of Cs, Sr and Tcen_AU
dc.typeConference Paperen_AU

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