scholarly journals INFLUENCE OF HIGH LEVEL WASTE SALTS ON MOVEMENT OF STRONTIUM AND CESIUM IN SAVANNAH RIVER PLANT SOIL.

1968 ◽  
Author(s):  
J.W. Fenimore ◽  
J.H. Jr. Horton
Keyword(s):  
High Level Waste ◽  
Savannah River ◽  
Plant Soil ◽  
Savannah River Plant ◽  
High Level

Study of Melted Synroc Doped with Simulated High-Level Waste

1996 ◽  
Vol 465 ◽  
Author(s):  
I. A. Sobolev ◽  
S. V. Stefanovsky ◽  
S. V. Ioudintsev ◽  
B. S. Nikonov ◽  
B. I. Omelianenko ◽  
...  
Keyword(s):  
Bulk Composition ◽  
Barometric Pressure ◽  
High Level Waste ◽  
Savannah River ◽  
Savannah River Plant ◽  
High Level ◽  
A Minor ◽  
Simulated High Level Waste ◽  
Additional Phase

ABSTRACTPreparation 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.

scholarly journals Near-Surface Leaching Studies of Pb-Implanted Savannah River Waste Glass

1981 ◽  
Vol 11 ◽  
Author(s):  
G. W. Arnold ◽  
C. J. M. Northrup ◽  
N. E. Bibler
Keyword(s):  
Energy Deposition ◽  
Surface Damage ◽  
High Level Waste ◽  
Savannah River ◽  
Near Surface ◽  
Ion Tracks ◽  
Savannah River Plant ◽  
High Level ◽  
Storage Times ◽  
Long Storage

Ion implantation into simulated nuclear waste glasses is a rapid means of producing near-surface energy deposition similar to that produced by α-recoil nuclei after long storage times (typically 103 – 106 years). For example, Dran, Maurette, and Petit1 used 200 keV Pb-ion implantations in glass at a fluence of 5 × 1012/cm2 to produce surface damage. This fluence is equivalent to approximately 2 × 1018 alpha-decays/cm3 which corresponds to approximately 106 years storage for glass containing Savannah River Plant (SRP) defense high-level waste (DHLW). These authors1 found that this fluence value corresponded to a critical fluence (Φc) for enhanced etching (a factor of 20 increase as inferred by step-height changes) for several silicate glasses when etched in a NaCl solution at 100°C. This critical fluence value also corresponds very well with the fluence at which significant overlap of individual ion tracks occurs.

Effects of Alpha, Gamma, and Alpha-Recoil Radiation on Borosilicate Glass Containing Savannah River Plant Defense High-Level Nuclear Waste

1981 ◽  
Vol 6 ◽  
Author(s):  
Ned E. Bibler
Keyword(s):  
Borosilicate Glass ◽  
Deionized Water ◽  
Savannah River ◽  
Γ Radiation ◽  
Leach Rate ◽  
Geologic Storage ◽  
Savannah River Plant ◽  
Pb Ions ◽  
High Level ◽  
Doped Glass

ABSTRACTAt the Savannah River Plant, the reference process for the immobilization of defense high-level waste (DHLW) for geologic storage is vitrification into borosilicate glass. During geologic storage for 106y, the glass would be exposed to ∼3 × 1010 rad of β radiation, ∼1010 rad of γ radiation, and 1018 particles/g glass for both α and α-recoil radiation. This paper discusses tests of the effect of these radiations on the leachability and density of the glass. No effect of the radiations was detected that reduced the effectiveness of the glass for long-term storage of DHLW even at doses corresponding to 106 years storage for the actual glass. For the tests, glass containing simulated DHLW was prepared from frit of the reference composition. Three methods were used to irradiate the glass: external irradiations with beams of ∼200 keV or Pb ions, internal irradiations with Cm–244 doped glass, and external irradiations with Co–60 γ rays. Results with both Xe and Pb ions indicate that a dose of 3 × 1013 ions/cm2 (simulating >106 years storage) does not significantly increase the leachability of the glass in deionized water. Tests with Cm–244 doped glass show no increase in leach rate in deionized water up to a dose of 1.3 × 1018 α and α-recoils/g glass. The density of the Cm–244 doped glass has decreased by 1% at a dose of 1018 particles/g glass. With γ-radiation, the density has changed by <0.05% at a dose of 8.5 × 1010 rad. Results of leach tests in deionized water and brine indicated that this very large dose of γ-radiation increased the leach rate by only 20%. Also, the leach rates are 3 to 4 times lower in brine.

Adaptation of CCIM Technology for HLW Treatment: Results of Research and Development

2010 ◽  
Author(s):  
Vladimir Lebedev ◽  
Sergey Stefanovsky ◽  
Alexander Kobelev ◽  
Fyodor Lifanov ◽  
Sergey Dmitriev
Keyword(s):  
High Level Waste ◽  
Cold Crucible ◽  
Savannah River ◽  
Treatment Results ◽  
Auxiliary Equipment ◽  
Automated Control ◽  
Automated Control System ◽  
New Perspective ◽  
High Level ◽  
River Site

Results of feasibility tests of application of Cold Crucible Inductive Melting (CCIM) technology to high level waste (HLW) treatment on examples of Savannah River Site, USA, and PA “Mayak”, Russia, HLW, carried out at SIA Radon, and results of design of new perspective bench-scale HLW vitrification facility are presented in this report. Full-scale low level waste (LLW) vitrification plant is under operation at Radon since 2003. Successful Radon experience aroused an interest to this technology from US DOE. Since 2001 Radon performed tests on vitrification of surrogates of various types of HLW stored at US DOE Sites. Process variables were determined and vitrified wastes were characterized in details. Since 2007 Radon was a subcontractor in the project on design and construction of a new CCIM based vitrification facility at PA “Mayak”. From preliminary tests on Mayak HLW surrogates the main technological features of CCIM process were determined and principles of the process control were formulated. Radon performed the design of the cold crucible and automated control system. On the base of analysis of previously and newly obtained data the main requirements to designing of cold crucible melters and auxiliary equipment, intended for actual HLW treatment, were worked out.

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