Release of uranium and plutonium from the EBR-II ceramic waste form

被引：0

作者：

Morss, LR ^{[1
]}

Ebert, WL ^{[1
]}

机构：

[1] Argonne Natl Lab, Div Chem Technol, Argonne, IL 60439 USA

来源：

ENVIRONMENTAL ISSUES AND WASTE MANAGEMENT TECHNOLOGIES IN THE CERAMIC AND NUCLEAR INDUSTRIES VII | 2002年 / 132卷

关键词：

D O I：

暂无

中图分类号：

X [环境科学、安全科学];

学科分类号：

08 ; 0830 ;

摘要：

A ceramic waste form (CWF) has been developed to immobilize radioactive electrorefiner salt from the electrometallurgical treatment of spent metallic fuel from the experimental breeder reactor EBR-II. Tests are being carried out to qualify CWF for disposal in a high-level waste repository. There are two major phases in U/Pu-loaded CWF, sodalite (Na8Al6Si6O24Cl2) and glass; and two important minor phases, halite (NaCl) and oxide (U,Pu)O-2. The (U,Pu)O-2 phase is present as colloid-sized particles in the glass, near sodalite-glass phase boundaries. Tests have been conducted to measure the release behavior of the (U,Pu)O-2 particles as the CWF corrodes. The releases of matrix and radioactive elements from CWF samples into water were determined from tests in which crushed material was reacted with water at 90 or 120 degreesC for durations from 7 to 365 days. Colloids in the test solutions were characterized by sequential filtration, followed by analysis of filtrates for cations. Plutonium is released partially as (U,Pu)O-2 colloids similar to the particles in the uncorroded CWT.

引用

页码：389 / 396

页数：8

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