日本原子力学会誌
Online ISSN : 2186-5256
Print ISSN : 0004-7120
984. 高レベル放射性廃棄物地層処分システムの初期過渡状態の解析
大江 俊昭安 俊弘池田 孝夫菅野 毅千葉 保塚本 政樹中山 真一長崎 晋也
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35 巻 (1993) 5 号 p. 420-437

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This paper describes the validity of two assumptions usually accounted for performance analyses of engineered barriers; nuclide release starts at 1, 000 yr after backfilling of packages, and the chemical environment around the package is kept under a reducing condition. Analyses by several computer codes such as TOUGH, PHREEQE and CHEMSIMUL were conducted to estimate the followings: the time at which the buffer material is fully saturated with water, geochemical conditions of the pore water, and hydrogen gas production due to package corrosion and to water radiolysis. Calculation results indicate, if bentonite is used as buffer material, that the buffer layer becomes saturated within several decades and that a reducing environment is accomplished due to mineral oxidation reactions in bentonite, with resulting in less corrosion of waste packages than expected from the previous experimental corrosion data. Hydrogen production due to package corrosion by the pore water is more dominant than that by steam corrosion or water radiolysis, and further discussion is still required for specifying the possible mechanical and chemical effects on the engineered barrier system due to produced hydrogen.

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© by the Atomic Energy Society of Japan
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