Migration of plutonium in a simulated engineered barrier system consisting of waste glass and compacted bentonite

被引：2

作者：

Inagaki, Y ^{[1
]}

Saito, R ^{[1
]}

Furuya, H ^{[1
]}

Idemitsu, K ^{[1
]}

Arima, T ^{[1
]}

Banbu, T ^{[1
]}

Maeda, T ^{[1
]}

Matsumoto, S ^{[1
]}

Tamura, Y ^{[1
]}

Kikkawa, S ^{[1
]}

机构：

[1] Kyushu Univ, Dept Nucl Engn, Fukuoka 8128581, Japan

来源：

SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXII | 1999年 / 556卷

关键词：

D O I：

10.1557/PROC-556-1083

中图分类号：

X [环境科学、安全科学];

学科分类号：

08 ; 0830 ;

摘要：

In a simulated engineered barrier system consisting of a simulated HLW glass doped with Pu, a compacted bentonite and water under reducing conditions, migration tests of Pu from the glass into the bentonite through water were performed. The following results were obtained: (1) The presence of bentonite enhances the glass dissolution while it has no remarkable influence on the concentration of Pu dissolved species in the solution. (2) Only a small part of the leached Pu, which may correspond to the dissolved species, can diffuse into the bentonite with the apparent diffusion coefficient of 3 x 10(-14)m(2)/s. (3) Interactions between the glass and the bentonite have no remarkable influence on the diffusion of Pu.

引用

页码：1083 / 1090

页数：4

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