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AbstractAbstract
[en] A study was carried out to determine the extent of corrosion for a range of low-level waste container materials in contact with simulated resin bead decontamination wastes. The materials included metals and high-density polyethylene. Tests were also conducted on mechanical stability of the decontamination resin wastes, solidified in cement and vinyl ester-styrene, during thermal cycling between 60/degree/C and /minus/40/degree/C. 12 refs., 20 figs., 12 tabs
Primary Subject
Secondary Subject
Source
Jun 1988; 58 p; BNL-NUREG--51699-VOL.5; NTIS, PC A04/MF A01 - US Govt. Printing Office. - OSTI as TI89002303
Record Type
Report
Literature Type
Progress Report
Report Number
Country of publication
BWR TYPE REACTORS, CORROSION, DECONTAMINATION, ION EXCHANGE, LOW-LEVEL RADIOACTIVE WASTES, OCCUPATIONAL EXPOSURE, OXIDATION, POLYETHYLENES, POLYSTYRENE, PROGRESS REPORT, PWR TYPE REACTORS, RADIOACTIVE WASTE PROCESSING, RADIOACTIVE WASTES, RESINS, SOLIDIFICATION, STAINLESS STEELS, THERMAL CYCLING, WASTE MANAGEMENT
ALLOYS, CARBON ADDITIONS, CHEMICAL REACTIONS, CLEANING, ENRICHED URANIUM REACTORS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MANAGEMENT, MATERIALS, ORGANIC COMPOUNDS, ORGANIC POLYMERS, POLYMERS, POLYOLEFINS, POLYVINYLS, POWER REACTORS, RADIOACTIVE MATERIALS, REACTORS, STEELS, THERMAL REACTORS, WASTE PROCESSING, WASTES, WATER COOLED REACTORS, WATER MODERATED REACTORS
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