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

被引：119

作者：

Wilmarth, William R. ^{[2
]}

Lumetta, Gregg J. ^{[1
]}

Johnson, Michael E. ^{[3
]}

Poirier, Michael R. ^{[2
]}

Thompson, Major C. ^{[2
]}

Suggs, Patricia C. ^{[4
]}

Machara, Nicholas P. ^{[5
]}

机构：

[1] Pacific NW Natl Lab, Richland, WA 99352 USA

[2] Savannah River Natl Lab, Aiken, SC USA

[3] CH2M Hill Plateau Remediat Co, Richland, WA USA

[4] US DOE, Aiken, SC USA

[5] US DOE, Off Technol Innovat & Dev, Germantown, MD USA

来源：

SOLVENT EXTRACTION AND ION EXCHANGE | 2011年 / 29卷 / 01期

关键词：

Pretreatment; radioactive waste; cross-flow filter; rotary microfilter; cesium ion exchange; cesium solvent extraction; crystalline silicotitanate; monosodium titanate; SAVANNA RIVER SITE; HIGH-LEVEL WASTE; SOLVENT-EXTRACTION RECOVERY; TANK WASTE; CRYSTALLINE SILICOTITANATE; ACTINIDE SEPARATIONS; CESIUM; REMOVAL; HANFORD; STRONTIUM;

D O I：

10.1080/07366299.2011.539134

中图分类号：

O6 [化学];

学科分类号：

0703 ;

摘要：

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.

引用

页码：1 / 48

页数：48

共 121 条

[1]

[Anonymous], 1995, PNL10750

[2]

ATOR RA, 1984, 831714 DPSP SAV RIV

[3]

BEARD SJ, 1962, HW75051 GEN EL

[4]

BLANCHARD DL, 2000, PNWD3028