書誌事項
- タイトル別名
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- Interlaboratory Modeling for Performance Assessment of Engineered Barriers in High-Level Radioactive Waste Disposal.
- コウ レベル ホウシャセイ ハイキブツ ノ チソウ ショブン ニ オケル ジン
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Migration of radionuclides released from waste solid in engineered barriers was modeled. Mass fluxes of 99Tc, 135Cs and 237Np at the buffer/rock interface were calculated. The model features (1) analysis on groundwater flow around a disposal pit, which shows that in a buffer material of compacted bentonite, the groundwater flow is negligible and the mass transport can be assumed diffusion controlled, (2) analysis on dissolution of waste glass and resulting release of radionuclides from the solid by considering geochemical interactions of groundwater with glass waste form, overpack material and buffer material, (3) analysis on migration of a redox-sensitive element, with the oxidation-reduction reactions incorporated, and (4) analysis on effects of waste geometries by comparing fluxes resulting from a cylindrical waste package and a spherical one.<BR>The study is the first stage for fulfilling our goal to construct a scientifically-sound, integrated performance assessment model for geologic disposal of high-level radioactive waste. The effort presented in this study will help us define future studies to be directed.
収録刊行物
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- 日本原子力学会誌
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日本原子力学会誌 34 (4), 342-364, 1992
一般社団法人 日本原子力学会
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詳細情報 詳細情報について
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- CRID
- 1390001206550993536
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- NII論文ID
- 130003747231
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- NII書誌ID
- AN00188477
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- ISSN
- 21865256
- 00047120
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- NDL書誌ID
- 3770732
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- 本文言語コード
- ja
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- データソース種別
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- JaLC
- NDL
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- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可