Evaluation of ceramic and polymeric materials for use in engineered barrier systems
Ceramic materials evaluated in the screening studies were Al/sub 2/O/sub 3/ (99.8%), mullite, vitreous silica, BaTiO/sub 3/, CaTiO/sub 3/, CaZrO/sub 3/, CaTiSiO/sub 5/, TiO/sub 2/, ZrSiO/sub 4/, basalt, Pyroceram 9617, and Marcor code 9658 machinable glass ceramic. One grade of graphite (Toyotanso IB-11) was also evaluated. Demineralized water, a synthetic Hanford groundwater, and a synthetic NaCl brine solution were used in the screening tests. Demineralized water was used in all five of the leach tests, but the other solutions were only used in the static leach tests at 150 and 250/sup 0/C. Based on the results obtained, graphite appears to be the most leach resistant of the materials tested with the two grades of alumina being the best of the ceramic materials. Titanium dioxide and ZrO/sub 2/ are the most leach resistant of the remaining materials. Candidate materials from all three general classes of polymers (thermoplastics, thermosets, and elastomers) were considered in the selection of materials. Selected groups of polymers were tested in the flowing autoclave at 150, 200, and 250/sup 0/C with some polymers being further tested at the next higher temperature. Next, selected samples were exposed to gamma radiation. These samples were then submitted for tensile and elongation measurements. Selected samples which appeared promising from both autoclave and radiation testing were further evaluated by impact tests. The materials that appeared most promising after autoclave testing were the EPDM rubbers, polyphenylene sulfide, poly(ethylene-tetrafluoroethylene) copolymer, and polyfurfuryl alcohol. The radiation dose had little effect on polyfurfuryl alcohol and polyphenylene sulfide samples; very significant decreases in elongation were observed for the fluorocarbon copolymer and the EPDM rubbers. While the polyphenylene sulfide and polyfurfuryl alcohol showed little change in impact strength, poly(ethylene-tetrafluoroethylene) decreased in impact strength.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6608767
- Report Number(s):
- PNL-SA-8672; CONF-801124-44; TRN: 81-006179
- Resource Relation:
- Conference: 3. annual meeting of the Materials Research Society, Boston, MA, USA, 17 Nov 1980
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BASALT
LEACHING
CERAMICS
ELASTOMERS
ELONGATION
IMPACT STRENGTH
PHYSICAL RADIATION EFFECTS
TENSILE PROPERTIES
GRAPHITE
ORGANIC POLYMERS
THERMOPLASTICS
ALUMINIUM OXIDES
BARIUM COMPOUNDS
BRINES
CALCIUM COMPOUNDS
ENGINEERED SAFETY SYSTEMS
EXPERIMENTAL DATA
GAMMA RADIATION
GROUND WATER
RADIOACTIVE WASTE DISPOSAL
TITANATES
TITANIUM OXIDES
ZIRCONATES
ZIRCONIUM OXIDES
ALKALINE EARTH METAL COMPOUNDS
ALUMINIUM COMPOUNDS
CARBON
CHALCOGENIDES
DATA
DISSOLUTION
ELECTROMAGNETIC RADIATION
ELEMENTS
HYDROGEN COMPOUNDS
IGNEOUS ROCKS
INFORMATION
IONIZING RADIATIONS
MANAGEMENT
MECHANICAL PROPERTIES
NONMETALS
NUMERICAL DATA
ORGANIC COMPOUNDS
OXIDES
OXYGEN COMPOUNDS
PETROCHEMICALS
PETROLEUM PRODUCTS
PLASTICS
POLYMERS
RADIATION EFFECTS
RADIATIONS
ROCKS
SEPARATION PROCESSES
TITANIUM COMPOUNDS
TRANSITION ELEMENT COMPOUNDS
VOLCANIC ROCKS
WASTE DISPOSAL
WASTE MANAGEMENT
WATER
ZIRCONIUM COMPOUNDS
360205* - Ceramics
Cermets
& Refractories- Corrosion & Erosion
360403 - Materials- Polymers & Plastics- Mechanical Properties- (-1987)
360405 - Materials- Polymers & Plastics- Degradation & Erosion- (-1987)
052002 - Nuclear Fuels- Waste Disposal & Storage