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High Level Liquid Waste Solidification Using a “Cold” Crucible Induction Melter

Published online by Cambridge University Press:  21 March 2011

Andrei V. Demine ,
Nina V. Krylova ,
Pavel P. Polyektov ,
Igor N. Shestoperov ,
Tatyana V. Smelova ,
Valerii F. Gorn  and
Gennadii M. Medvedev
Andrei V. Demine
Affiliation:
SSC RF VNIINM, Moscow, Russia
Nina V. Krylova
Affiliation:
SSC RF VNIINM, Moscow, Russia
Pavel P. Polyektov
Affiliation:
SSC RF VNIINM, Moscow, Russia
Igor N. Shestoperov
Affiliation:
SSC RF VNIINM, Moscow, Russia
Tatyana V. Smelova
Affiliation:
SSC RF VNIINM, Moscow, Russia
Valerii F. Gorn
Affiliation:
IA.MAYAK., Ozersk, Russia
Gennadii M. Medvedev
Affiliation:
IA.MAYAK., Ozersk, Russia
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Abstract

At the present time the primary problem in a closed nuclear fuel cycle is the management of high level liquid waste (HLLW) generated by the recovery of uranium and plutonium from spent nuclear fuel. Long-term storage of the HLLW, even in special storage facilities, poses a real threat of ecological accidents. This problem can be solved by incorporating the radioactive waste into solid fixed forms that minimize the potential for biosphere pollution by long-lived radionuclides and ensure ecologically acceptable safe storage, transportation, and disposal. In the present report, the advantages of a two-stage HLLW solidification process using a “cold” crucible induction melter (CCIM) are considered in comparison with a one-stage vitrification process in a ceramic melter.

This paper describes the features of a process and equipment for a two-stage HLLW solidification technology using a “cold” crucible induction melter (CCIM) and identifies the advantages compared to a one-stage ceramic melter. A two-stage pilot facility and the technical characteristics of the equipment are described using a once-through evaporator and cold-crucible induction melter currently operational at the IA.Mayak. facility in Ozersk, Russia. The results of pilot-plant tests with simulated HLLW to produce a phosphate glass are described. Features of the new mineral-like waste form matrices synthesized by the CCIM method are also described. Subject to further development, the CCIM technology is planned to be used to solidify all accumulated HLLW at Mayak – first to produce borosilicate glass waste forms and then mineral-like waste forms.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 663: Symposium – Scientific Basis for Nuclear Waste management XXIV , 2000 , 27
Copyright
Copyright © Materials Research Society 2001

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References

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