Effects of Radiation Exposure on SRL 131 Composition Glass in a Steam Environment
Monoliths of SRL 131 borosilicate glass were irradiated in a saturated air-steam environment, at temperatures of 150°C, to examine the effects of radiation on nuclear waste glass behavior. Half of the tests used actinide and Tc-99 doped glass and were exposed to an external ionizing gamma source, while the remaining glass samples were doped only with uranium and were reacted without any external radiation exposure. The effects of radiation exposure on glass alteration and secondary phase formation were determined by comparing the reaction rates and mineral paragenesis of the two sets of samples.
D. J. Wronkiewicz et al., "Effects of Radiation Exposure on SRL 131 Composition Glass in a Steam Environment," Materials Research Society Symposium Proceedings, vol. 333, pp. 259-267, Materials Research Society (MRS), Nov 1994.
The definitive version is available at https://doi.org/10.1557/PROC-333-259
17th Materials Society Symposium (1993: Nov. 29-Dec. 3, Boston, MA)
Geosciences and Geological and Petroleum Engineering
Keywords and Phrases
Borosilicate Glass; Environmental Protection; Geological Repositories; Radiation Damage; Radiation Effects; Mineral Paragenesis; Nuclear Waste Glass; Radiation Exposure; Radioactive Waste Encapsulation
International Standard Book Number (ISBN)
International Standard Serial Number (ISSN)
Article - Conference proceedings
© 1994 Materials Research Society (MRS), All rights reserved.