The feasibility of incorporating tritium wastes in epoxy resin
Description
Epoxy resin shows its suitability to incorporate tritium, in form of tritiated linoleic acid produced by TROC-process (tritium removal by organic compound). The compressive strength of the polymer product can be improved through the addition of silica powder and by irradiation up to 100 Mrad. Increasing linoleic acid content decreases the compressive strength of the product. The type and the temperature of the immersion medium also affects the compressive strength. The epoxy/waste product was thermal stable up to 450oC. The leaching rates of tritium from the epoxy resin product under different experimental conditions were in the range of 1.2x10-5 to 1.3x10-7 gcm-2d-1. Based on the obtained data, it is recommended to dispose the epoxy/waste product in salt formation. (author) 13 figs., 1 tab., 16 refs
Additional details
Publishing Information
- Journal Title
- Radioactive Waste Management and the Nuclear Fuel Cycle
- Journal Volume
- 17
- Journal Issue
- 1
- Journal Page Range
- p. 1-17.
- ISSN
- 0739-5876
- CODEN
- RWMCD4
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- Switzerland
- INIS RN
- 24016273
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- EPOXIDES; EXPERIMENTAL DATA; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE PROCESSING; TRITIUM
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; DATA; HYDROGEN ISOTOPES; INFORMATION; ISOTOPES; LIGHT NUCLEI; MANAGEMENT; NUCLEI; NUMERICAL DATA; ODD-EVEN NUCLEI; ORGANIC COMPOUNDS; ORGANIC OXYGEN COMPOUNDS; RADIOISOTOPES; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE PROCESSING; YEARS LIVING RADIOISOTOPES