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Study of Melted Synroc Doped with Simulated High-Level Waste

Published online by Cambridge University Press:  03 September 2012

I. A. Sobolev ,
S. V. Stefanovsky ,
S. V. Ioudintsev ,
B. S. Nikonov ,
B. I. Omelianenko  and
A. V. Mokhov
I. A. Sobolev
Affiliation:
SIA “Radon”, 7-th Rostovskii line 2/14, Moscow 119121, Russia, fax: 7–095–919–3194
S. V. Stefanovsky
Affiliation:
SIA “Radon”, 7-th Rostovskii line 2/14, Moscow 119121, Russia, fax: 7–095–919–3194
S. V. Ioudintsev
Affiliation:
Institute of Geology of Ore Deposits, Staromonetny line 35,. Moscow 109017, Russia
B. S. Nikonov
Affiliation:
Institute of Geology of Ore Deposits, Staromonetny line 35,. Moscow 109017, Russia
B. I. Omelianenko
Affiliation:
Institute of Geology of Ore Deposits, Staromonetny line 35,. Moscow 109017, Russia
A. V. Mokhov
Affiliation:
Institute of Geology of Ore Deposits, Staromonetny line 35,. Moscow 109017, Russia
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Abstract

Preparation and characterization of inductively-melted Synroc containing 20 wt% simulated plant “Mayak” reprocessing waste were performed. The sample bulk composition was as follows, (in wt.%): 55.4 TiO2; 15.8 ZrO2; 7.5 CaO; 7.4 BaO; 4.3 Al2O3 2.0 MnO; 1.8 SiO2; 0.7 Na2O; 1.9 K2O, 0.5 Ce2O3; 1.0 UO2; 0.9 NiO; 0.6 Cr2O3, and 0.2 FeO. The sample was produced by melting in air at 1550–1600 °C under barometric pressure. It is composed of a few crystalline phases and a minor glass phase. Most of the phases (hollandite, zirconolite, perovskite and rutile) are similar to the analogous phases found in the other Synroc formulations. An additional phase with average composition, wt.%: 59.8 TiO2; 15.6 CaO; 7.0 UO2; 5.6 ZrO2; 4.7 MnO; 4.1 Ce2O3, and 1.8 Al2O3 was found. Some elements (Ba, Si, Ni, K, Na, Fe) were present in the phase in negligible quantities. Its formula (Ca2.65U0.3Ce0.2)(Ti7.3Mn0.6Zr0.4Al0.3)O20.0 is rather close to a rare mineral uhligite - Ca3(Ti,Zr,Al)9O20. Another possible counterpart of the phase is murataite-like mineral previously described in tailored ceramic designed for Savannah River Plant wastes fixation. This phase as well as zirconolite are the major host for U in the sample Preliminary data on the material leachability in water at 350 °C and 50 MPa have been obtained Uranium contents in the solution were about 1 ppb and close to the uranium dioxide solubility in deionized water under the same P-T conditions.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 465: Symposium II – Scienfific Basis for Nuclear Waste Management XX , 1996 , 363
Copyright
Copyright © Materials Research Society 1997

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References

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