Description: Das Projekt "Nuclear waste forms characterisation, 1988-1991" wird vom Umweltbundesamt gefördert und von European Commission, Joint Research Centre (JRC). Institute for Transuranium Elements (ITU) durchgeführt. Objective: To characterize vitrified high-level waste forms and unprocessed spent fuel with respect to properties relevant to their behaviour under conditions of long-term storage, i.e. radioactive nuclide inventory, thermal conductivity, thermal and mechanical stability, redistribution of actinides and fission products within waste materials, radiation damage, resistance to corrosive agents, and to investigate leaching of waste forms with various leachant compositions. General Information: Progress to end 1990. Leach tests on active glasses showed no noticeable differences in comparison with non-active specimens subject to the same treatment except for the behaviour of the actinides which needs further study. Leaching tests on high burn-up spent fuel samples were initiated. Tests on the characterization of cement matrix for solidification of ILLW were concluded, and new analytical methods were applied (Inductively coupled plasma mass spectrometry). A prototype of an autoclave for the leaching under realistic resitory conditions was developed. A parametric study ( determination of Eh, pH, T, (O2), (CO3)), of UO2 oxidation by leaching was initiated. Scouting experiments with irradiated UO2 were carried out. A neutron counting system is being developed for passive neutron interrogation of individual fuel rods. Gamma-spectroscopy is performed using an existing facility. Interpretation of the measured signatures is achieved through isotopic correlations. A micro-gamma scanning device to measure the distribution ofamma emitters in waste forms went into operation. A study of the mechanical state and of radiation damage on matrix dissolution was launched. Results obtained in this context were published in a EUR report and presented at 4 occasions at international conferences. Detailed description of work foreseen in 1991 (expected results). New autoclaves for spent fuel and glass leaching experiments will be tested and used. Leach tests on selected active samples with fully characterized structures will continue, as well as tests with SIM fuel and, to a limited extent, ceramic waste forms. A laser cutting device for the machining of controlled flaws in fuel pins will be installed. R7T7-glasses and spent fuels will be characterized in a cooperation with CEA-Marcoule and KfK-INE Karlsruhe. High burn-up pins from BR-3 will be leached at pre-termined oxygen potentials A Community exercise for the selection and standardization of waste characterization procedures will be launched. New analytical methods will be applied to Np speciation. NDA will be applied to pins of spent fuel. Neutron counting equipment will be calibrated using a Cf-252 source. Gamma/neutron emission tomography will be installed for the characterisation of spent fuel cross sections. Radiation damage studies will continue. Short description of evolution of work in 1992 Leach testing of glasses and spent fuel samples will continue. Characterization techniques will be refined. ...
Types:
SupportProgram
Origin: /Bund/UBA/UFORDAT
Tags: Karlsruhe ? Glas ? Keramik ? Zement ? Brennstoff ? Neutronenstrahlung ? Raffination ? Transuran ? Brennelement ? Europäische Kommission ? Gammaspektroskopie ? Langzeitwirkung ? Laser ? Radioaktiver Abfall ? Pflanzensamen ? Sauerstoff ? Strahlenschaden ? Temperaturverteilung ? Thermodynamik ? Probenaufbereitung ? Mechanisches Verfahren ? Actinoide ? Isotopentechnik ? Korrelationsanalyse ? Massenspektrometrie ? Radionuklid ? Strahlenexposition ? Emissionsquelle ? Verfahrensparameter ? Wärmeleitfähigkeit ? Korrosion ? Abfalllagerung ? Oxidation ? pH-Wert ? Bewertungsverfahren ? Informationsvermittlung ? Reaktor ? Abfallanalyse ? Sauerstoffgehalt ? Stichprobe ? Langzeitspeicherung ? Abfallzusammensetzung ? Studie ? Emission ? Analyseverfahren ? Evolution ? Auslaugung ? Leitfähigkeit ? Thermisches Verfahren ? Auflösen ? Abfall ? Forschungseinrichtung ? Radioaktivität ? Schadstoffverhalten ? Standardisierung ? Zusammenarbeit ? Gutachten ? Neptunium ? Auswertungsverfahren ? Neutronen ? Spaltprodukt ? Speziation [Chemie] ? Prototyp ? Untersuchungsprogramm ?
Region: Baden-Württemberg
Bounding box: 9° .. 9° x 48.5° .. 48.5°
License: cc-by-nc-nd/4.0
Language: Deutsch
Time ranges: 1988-01-01 - 1992-01-01
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