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Glass Waste Form Performance for Disposal of the Cesium and Strontium Concentrate Resulting From the Partitioning of HLW

Published online by Cambridge University Press:  10 February 2011

A.S. Aloy ,
O.A. Iskhakova ,
T.I. Kol‘tsova  and
A.V. Trofimenko
A.S. Aloy
Affiliation:
RPA »V.G.Khlopin Radium Institute, St. Petersburg, Russia, aloy@rian.spb.su
O.A. Iskhakova
Affiliation:
RPA »V.G.Khlopin Radium Institute, St. Petersburg, Russia
T.I. Kol‘tsova
Affiliation:
RPA »V.G.Khlopin Radium Institute, St. Petersburg, Russia
A.V. Trofimenko
Affiliation:
RPA »V.G.Khlopin Radium Institute, St. Petersburg, Russia
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Abstract

The recent advances in HLW partitioning indicate that cesium–137 and strontium–90 can be separated in the form of a pure concentrate. Based on this concentrate the glass RT2–1 containing 4.7 wt.% Cs2O and 2.7 wt.% SrO was selected for more intensive and wider studies to predict long-term performance of this waste form under repository conditions.

Leach tests were made in distilled and mineralized water before and after crystallization at 20, 90 and 130°C.

Fully devitrified glass contained only one crystalline phase corresponding to the pollucite structure.

Information

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 506: Symposium – Scientific Basis for Nuclear Waste Management XXI , 1997 , 901
Copyright
Copyright © Materials Research Society 1998

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References

REFERENCES

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