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Immobilization of Radioactive Iodine Using AgI Vitrification Technique for the TRU Wastes Disposal: Evaluation of Leaching and Surface Properties

Published online by Cambridge University Press:  01 February 2011

Tomofumi Sakuragi ,
Tsutomu Nishimura ,
Yuji Nasu ,
Hidekazu Asano ,
Kuniyoshi Hoshino  and
Kenji Iino
Tomofumi Sakuragi
Affiliation:
EBS Technology Research Project, Radioactive Waste Management Funding and Research Center, Pacific Square Tsukishima, 1-15-7, Tsukishima, Chuo City, Tokyo 104-0052, Japan
Tsutomu Nishimura
Affiliation:
EBS Technology Research Project, Radioactive Waste Management Funding and Research Center, Pacific Square Tsukishima, 1-15-7, Tsukishima, Chuo City, Tokyo 104-0052, Japan
Yuji Nasu
Affiliation:
EBS Technology Research Project, Radioactive Waste Management Funding and Research Center, Pacific Square Tsukishima, 1-15-7, Tsukishima, Chuo City, Tokyo 104-0052, Japan
Hidekazu Asano
Affiliation:
EBS Technology Research Project, Radioactive Waste Management Funding and Research Center, Pacific Square Tsukishima, 1-15-7, Tsukishima, Chuo City, Tokyo 104-0052, Japan
Kuniyoshi Hoshino
Affiliation:
Hitachi-GE Nuclear Energy, 3-1-1 Saiwai, Hitachi, Ibaraki 317-8511, Japan
Kenji Iino
Affiliation:
Hitachi-GE Nuclear Energy, 3-1-1 Saiwai, Hitachi, Ibaraki 317-8511, Japan
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Abstract

Iodine-129 collected from a reprocessing plant is regarded as the dominant nuclide in terms of safety for TRU wastes disposal in Japan. AgI vitrification (AgI-Ag2O-P2O5) is a potential iodine immobilization technique, which has the advantages of less iodine volatilization (low-temperature vitrification) and high volume reduction efficiency (approx. 1/25 the original waste volume). The iodine immobilization property can be evaluated by examining the surface condition of the AgI glass immersed in water. In this study, immersion tests have been performed on AgI glass in pure water in a 3% H2-N2 atmosphere at room temperature, and the surface characteristics have been examined. The thin layer (<4.3 μm) that is formed has been found to consist of AgI, which may act as a barrier, preventing leaching of glass components. The concepts behind the iodine release model have been proposed based on diffusion and the solubility of the components at the glass surfaces.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1107: Scientific Basis for Nuclear Waste Management XXXI , 2008 , 279
Copyright
Copyright © Materials Research Society 2008

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