Report on research and development work 1983 of the Institut fuer Nukleare Entsorgungstechnik
Description
The Institute for Nuclear Waste Processing undertook research and development work on the following key topics: 1) Inactive operation of the vitrification plant VA-3 to the point of transferal of the ceramic smelting apparatus K-3 together with other process components to the project PAMELA; 2) Active operational start-up of the facility for wet ashing Pu-waste (ALONA) in Mol, including the recovery of plutonium; 3) Study of properties of vitrified products of this technical process; 4) Laboratory trials on the separation of actinides and fission products from medium-level radioactive waste solutions; 5) Solidification of alpha-containing concentrates in a ceramic matrix, characterization of the products and process developmental work; 6) Study of the release of radionuclides from medium-level radioactive waste solutions by leaching and mechanical or thermal stress; 7) Development of stable containers for the final storage of highly radioactive vitrified products in salt; 8) Studies on analytical safety assurance for final storage in geological formations. A list of publications and lectures given by members of the Institute during 1983 is appended to the report. (orig./RB)
Availability note (English)
MF available from INIS under the Report Number.Abstract (German)
Das Institut fuer Nukleare Entsorgungstechnik fuehrte Arbeiten zu folgenden Schwerpunkten durch: Inaktiver Betrieb der Verglasungsanlage VA-3 bis zur Uebergabe des keramischen Schmelzers K-3 sowie anderer Verfahrenskomponenten an das Projekt PAMELA. Aktive Inbetriebnahme der Anlage zur Nassveraschung von Pu-Abfaellen (ALONA) in Mol einschliesslich der Rueckgewinnung des Plutoniums. Untersuchung der Eigenschaften von Glasprodukte aus dem technischen Prozess. Laborversuche zur Abtrennung von Aktiniden und Spaltprodukten aus mittelaktiven Abfalloesungen. Verfestigung alphahaltiger Konzentrate in einer keramischen Matrix, Charakterisierung der Produkte und verfahrenstechnische Entwicklungen. Untersuchung des Freisetzungsverhaltens von Radionukliden aus mittelaktiven Abfallprodukten bei Auslaugung sowie mechanischer oder thermischer Belastung. Entwicklung langzeitbestaendiger Behaelter fuer die Endlagerung hochaktiver Glasprodukte im Salz. Arbeiten zum analytischen Sicherheitsnachweis fuer Endlager in geologischen Formationen. Dem Bericht ist eine Liste von Veroeffentlichungen und Vortraegen der Mitarbeiter des Instituts aus dem Jahre 1983 angeschlossen. (orig./RB)
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Additional details
Additional titles
- Original title (German)
- Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1983 des Instituts fuer Nukleare Entsorgungstechnik
- Augmented title (English)
- Development of radioactive waste processing methods, characterization of solidified products or final storage
Publishing Information
- Imprint Pagination
- 36 p.
- Report number
- KFK--3692
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 15068437
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- BENCH-SCALE EXPERIMENTS; BIBLIOGRAPHIES; BOREHOLES; CEMENTS; CERAMICS; CORROSION; FISSION PRODUCT RELEASE; GLASS; HIGH-LEVEL RADIOACTIVE WASTES; LEACHING; MATHEMATICAL MODELS; PACKAGING; PLUTONIUM; QUALITY ASSURANCE; RADIOACTIVE WASTE FACILITIES; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTE STORAGE; RADIOACTIVE WASTES; SOLID WASTES; TESTING; VITRIFICATION; WET ASHING
- Descriptors DEC
- ACTINIDES; BUILDING MATERIALS; CAVITIES; CHEMICAL REACTIONS; DISSOLUTION; ELEMENTS; MANAGEMENT; MATERIALS; METALS; NUCLEAR FACILITIES; RADIOACTIVE MATERIALS; SEPARATION PROCESSES; STORAGE; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING; WASTE STORAGE; WASTES