4.1 Review

Review: Waste-Pretreatment Technologies for Remediation of Legacy Defense Nuclear Wastes

期刊

SOLVENT EXTRACTION AND ION EXCHANGE
卷 29, 期 1, 页码 1-48

出版社

TAYLOR & FRANCIS INC
DOI: 10.1080/07366299.2011.539134

关键词

Pretreatment; radioactive waste; cross-flow filter; rotary microfilter; cesium ion exchange; cesium solvent extraction; crystalline silicotitanate; monosodium titanate

资金

  1. U.S. Department of Energy, Office of Environmental Management
  2. U.S. Department of Energy [DE-AC05-76RL01830, DE-AC09-08SR22470]

向作者/读者索取更多资源

The U.S. Department of Energy (DOE) is responsible for retrieving, immobilizing, and disposing of radioactive waste generated during the production of nuclear weapons in the United States. The general strategy for treating the radioactive tank waste consists of pretreating the wastes by separating them into high-level and low-activity fractions. The high-level fraction will be immobilized in a glass form suitable for disposal in a geologic repository. The low-activity waste will be immobilized in a waste form suitable for on-site. This paper reviews recent developments in the application of pretreatment technologies to the processing of the DOE radioactive tank wastes.

作者

我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。

评论

主要评分

4.1
评分不足

次要评分

新颖性
-
重要性
-
科学严谨性
-
评价这篇论文

推荐

暂无数据
暂无数据