Behaviour of sintered glasses containing simulated high level wastes under repository conditions
Creators
- 1. Division Materiales Nucleares, Centro Atomico Bariloche, CNEA (Argentina)
Description
Within the framework of an IAEA-CNEA Research Contract established in 1992, we have studied the vitrification of simulated high level wastes (HLW) from reprocessed PHWR fuel on a laboratory scale by the alternative method of powder glass sintering. The HLW was added in a proportion of 10 wt% to alumino-borosilicate glass powder. The powder mixture was treated using the procedure of cold pressing and subsequent sintering at about 1000K. The microstructures of the sintered samples were analyzed by optical microscopy and SEM. Water corrosion tests were done in different aqueous media. Devitrification studies were conducted by heat-treating the samples at 950, 1000, 1050 and 1100K for 3, 30, 300 and 3000 h. Values of the corrosion resistance of the studied glasses, were similar to those found in the literature for waste forms produced by melting technology. We have obtained promising results indicating that the glass sintering method could be an interesting alternative for immobilization for not only high level wastes but intermediate level wastes. (author)
Additional details
Publishing Information
- ISBN
- 978-92-0-106007-5
- Imprint Title
- Spent fuel and high level waste: Chemical durability and performance under simulated repository conditions. Results of a coordinated research project 1998-2004. Part 2: Results of a previously unpublished CRP: Performance of high level waste forms and packages under repository conditions. Results of a co-ordinated research project 1991-1998
- Imprint Pagination
- 289 p.
- Journal Page Range
- [16 p.]
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1563(companion CD Pt. 2)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 42024381
- Subject category
- S36: MATERIALS SCIENCE; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- BOROSILICATE GLASS; COLD PRESSING; CORROSION; CORROSION RESISTANCE; HIGH-LEVEL RADIOACTIVE WASTES; INTERMEDIATE-LEVEL RADIOACTIVE WASTES; MICROSTRUCTURE; OPTICAL MICROSCOPY; RADIOACTIVE WASTE DISPOSAL; SCANNING ELECTRON MICROSCOPY; SIMULATION; SINTERING; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K; VITRIFICATION; WASTE FORMS
- Descriptors DEC
- CHEMICAL REACTIONS; ELECTRON MICROSCOPY; FABRICATION; GLASS; MANAGEMENT; MATERIALS; MATERIALS WORKING; MICROSCOPY; PRESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; TEMPERATURE RANGE; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES
Optional Information
- Notes
- 25 refs, 5 figs, 7 tabs; This record replaces 39114068