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The leaching behavior of simulated HLW glass under repository condition 被引量:1

The leaching behavior of simulated HLW glass under repository condition
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摘要 As the multibarrier system has been adopted to dispose HLW glass in geological formation in many coun- tries, it was important to study the leaching behavior of vitrification under geological formation. This article describes the leaching behavior of simulated high level waste glass (90Nd/10), which can incorporate 16 wt.% simulated HLW in five kinds of geological media, such as granite, cement, bentonite, Fe3O4, etc. The durable experimental results show that the glass had less mass loss in granite and more mass loss in bentonite after a two-year leaching test. The SEM/XEDS analysis shows some element distributions on the leached specimen’s surface, i.e., Na, Si and Mg ele- ments were reduced on the specimen’s surface, whereas Ba, Al, and Fe were enriched on the specimen’s surface. As the multibarrier system has been adopted to dispose HLW glass in geological formation in many countries, it was important to study the leaching behavior of vitrification under geological formation. This article describes the leaching behavior of simulated high level waste glass (90Nd/10), which can incorporate 16 wt.% simulated HLW in five kinds of geological media, such as granite, cement, bentonite, Fe3O4, etc. The durable experimental results show that the glass had less mass loss in granite and more mass loss in bentonite after a two-year leaching test. The SEM/XEDS analysis shows some element distributions on the leached specimen's surface, i.e., Na, Si and Mg elements were reduced on the specimen's surface, whereas Ba, Al, and Fe were enriched on the specimen's surface.
出处 《Nuclear Science and Techniques》 SCIE CAS CSCD 2006年第3期158-163,共6页 核技术(英文)
关键词 滤取测试 花岗岩 斑脱土 多屏障系统 HLW-玻璃 Leaching test, Granite, Bentonite, Multi-barrier system, HLW-glass
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  • 2Van Iseghem P, Jiang Wei, Blanchaert M., et al. Mat Res Soc Symp Proc, 1996, 305:412
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  • 6Danvers. Standard test method for static leaching of monolithic waste forms for disposal of radioactive waste,ASTM Designation: C 1220-98

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