Recent experiments on fixation of high activity wastes in Karlsruhe
Description
A titanium dioxide containing glass in which more than 20 w.% of HAW oxides can homogeneously be incorporated has been developed for the solidification of the highly active waste solutions from the future large german reprocessing plant. Recently, investigations on the capacity of this glass for further ballast matter as Gd2O3, sulphate, chloride and fluoride became necessary. Results show that besides the 20 w.% of HAW oxides about 11 w.% Gd2O3 can be integrated in the system without substantial deterioration of the final product properties. 1.25% sulphate, 1.1% chloride and 5.5% fluoride represent maximum amounts when a homogeneous glass product shall be maintained. Moreover, Gd2O3 seems even to hinder the separation of the soluble molybdate phase from the glass melt. In addition to the work on borosilicate glass a similar glassceramic composition has been investigated which is described in view of its applicability for the fixation of highly active waste solutions. (orig.)
Availability note (English)
MF available from INIS under the Report Number.Abstract (German)
Fuer die Verfestigung der zu erwartenden hochradioaktiven Abfalloesungen aus einer grossen deutschen Wiederaufarbeitungsanlage fuer bestrahlte Kernbrennstoffe wurde ein titanoxidhaltiges Borosilikatglas entwickelt, in welches mehr als 20 Gew.% Gluehrueckstand der Abfalloesung homogen eingeschmolzen werden koennen. Neuerdings ergab sich die Notwendigkeit, die Aufnahmefaehigkeit dieses Glases fuer weitere Ballaststoffe wie Gd2O3, Sulfate, Chloride und Fluoride zu ueberpruefen. Die Untersuchungen zeigten, dass neben den 20% Spalt- und Korrosionsproduktoxiden noch etwa 11% Gd2O3 im Glas inkorporiert werden koennen ohne dass sich dessen Eigenschaften wesentlich verschlechtern. 1,25% Sulfat, 1,1% Chlorid und 5,5% Fluorid koennen maximal im Glasprodukt unter Beibehaltung seiner Homogenitaet eingebettet werden. Der Anteil an Gd2O3 scheint sogar die Ausscheidung der leichtloeslichen Molybdatphase aus der Glasschmelze zu behindern. Neben dem Borosilikatglas wird eine Glaskeramik auf Borosilikatglasbasis auf die Verwendbarkeit zur Fixierung von hochradioaktiven Abfalloesungen untersucht und beschrieben. (orig.)
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Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- KFK--2179
Conference
- Title
- 77. annual meeting and exposition of the American Ceramic Society.
- Dates
- 3 May 1975.
- Place
- Washington, D.C.
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 7252761
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BORON SILICATES; CERAMICS; GADOLINIUM OXIDES; GLASS; KERNFORSCHUNGSZENTRUM KARLSRUH; LEACHING; MELTING; MICROSTRUCTURE; PHASE STUDIES; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTES; RECRYSTALLIZATION; SOLIDIFICATION; SOLIDS
- Descriptors DEC
- BORON COMPOUNDS; CHALCOGENIDES; CRYSTAL STRUCTURE; DISSOLUTION; GADOLINIUM COMPOUNDS; GERMAN FR ORGANIZATIONS; MANAGEMENT; NATIONAL ORGANIZATIONS; OXIDES; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; RADIOACTIVE MATERIALS; RARE EARTH COMPOUNDS; SEPARATION PROCESSES; SILICATES; SILICON COMPOUNDS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES
Optional Information
- Notes
- 7 figs.; 4 tabs.; 12 refs.
- Secondary number(s)
- AED-Conf--75-241-032.