scholarly journals 2016 Update of Hanford Glass Property Models and Constraints for Use in Estimating the Glass Mass to be Produced at Hanford by Implementing Current Enhanced Glass Formulation Efforts

2016 ◽  
Author(s):  
John Vienna ◽  
Gregory Piepel ◽  
Dong-Sang Kim ◽  
Jarrod Crum ◽  
Charmayne Lonergan ◽  
...  
Keyword(s):  
Glass Mass ◽  
Glass Formulation ◽  
Glass Property

scholarly journals Vitrification of HLW Produced by Uranium/Molybdenum Fuel Reprocessing in COGEMA’s Cold Crucible Melter

2003 ◽  
Author(s):  
R. Do Quang ◽  
V. Petitjean ◽  
F. Hollebecque ◽  
O. Pinet ◽  
T. Flament ◽  
...  
Keyword(s):  
Atomic Energy Commission ◽  
Liquid Waste ◽  
Glass Layer ◽  
Cold Crucible ◽  
High Level Liquid Waste ◽  
Process Waste ◽  
Glass Formulation ◽  
High Level ◽  
Fuel Reprocessing ◽  
High Frequency Induction

The performance of the vitrification process currently used in the La Hague commercial reprocessing plants has been continuously improved during more than ten years of operation. In parallel COGEMA (industrial Operator), the French Atomic Energy Commission (CEA) and SGN (respectively COGEMA’s R&D provider and Engineering) have developed the cold crucible melter vitrification technology to obtain greater operating flexibility, increased plant availability and further reduction of secondary waste generated during operations. The cold crucible is a compact water-cooled melter in which the radioactive waste and the glass additives are melted by direct high frequency induction. The cooling of the melter produces a soldified glass layer that protects the melter’s inner wall from corrosion. Because the heat is transferred directly to the melt, high operating temperatures can be achieved with no impact on the melter itself. COGEMA plans to implement the cold crucible technology to vitrify high level liquid waste from reprocessed spent U-Mo-Sn-Al fuel (used in gas cooled reactor). The cold crucible was selected for the vitrification of this particularly hard-to-process waste stream because it could not be reasonably processed in the standard hot induction melters currently used at the La Hague vitrification facilities: the waste has a high molybdenum content which makes it very corrosive and also requires a special high temperature glass formulation to obtain sufficiently high waste loading factors (12% in molybednum). A special glass formulation has been developed by the CEA and has been qualified through lab and pilot testing to meet standard waste acceptance criteria for final disposal of the U-Mo waste. The process and the associated technologies have been also being qualified on a full-scale prototype at the CEA pilot facility in Marcoule. Engineering study has been integrated in parallel in order to take into account that the Cold Crucible should be installed remotely in one of the R7 vitrification cell. This paper will present the results obtained in the framework of these qualification programs.

scholarly journals Technical Status Report: Preliminary Glass Formulation Report for INEEL HAW

1998 ◽  
Author(s):  
D. Peeler ◽  
I. Reamer ◽  
J. Vienna ◽  
J.A. Crum
Keyword(s):  
Status Report ◽  
Technical Status ◽  
Glass Formulation

scholarly journals Low-temperature anomaly in disordered superconductors near Bc2 as a vortex-glass property

2018 ◽  
Vol 15 (1) ◽  
pp. 48-53 ◽  
Author(s):  
Benjamin Sacépé ◽  
Johanna Seidemann ◽  
Frédéric Gay ◽  
Kevin Davenport ◽  
Andrey Rogachev ◽  
...  
Keyword(s):  
Low Temperature ◽  
Temperature Anomaly ◽  
Vortex Glass ◽  
Disordered Superconductors ◽  
Glass Property

Measurement of Glass Corrosion in Boom Clay Disposal Conditions: First Results of the Experimental Programme 2000-2003 of SCK•CEN

2003 ◽  
Author(s):  
Karel Lemmens ◽  
Marc Aertsens ◽  
Ve´ra Pirlet ◽  
Norbert Maes ◽  
Hugo Moors ◽  
...  
Keyword(s):  
Low Temperature ◽  
Dissolution Rate ◽  
Near Field ◽  
Glass Frit ◽  
Glass Mass ◽  
Boom Clay ◽  
Glass Dissolution ◽  
Mass Losses ◽  
Dissolution Behaviour ◽  
First Results

To estimate the lifetime of vitrified high level waste (HLW-glass) in Boom Clay disposal conditions, the dissolution behaviour of waste glass has been studied with experiments performed in surface laboratories and in the HADES underground research facility of SCK·CEN since 1980. We present the main topics and first results of the SCK·CEN programme 2000–2003. This programme focuses on the following items: (1) the diffusion/sorption/precipitation of silica in Boom clay or backfill clay, (2) demonstration of glass dissolution behaviour in realistic test conditions, (3) the effect of presaturation of the clay with silica, and (4) the estimation of near field concentrations of critical isotopes. The experiments have shown so far that Si, released by the glass, is effectively immobilized by Boom Clay, but it can nevertheless diffuse into the clay without immediately precipitating. The dissolution rate of glass SON68 and SM539 is determined in Boom Clay at in situ density and at 30°C (this is the long-term temperature expected near the waste glass packages in a Boom Clay repository). The dissolution rates, based on glass mass losses, are constant during the first year, at ∼ 0.010 g.m−2.day−1 for glass SON68 and ∼ 0.012 g.m−2.day−1 for glass SM539. The addition of glass frit causes a decrease of the glass dissolution rate, both with glass SON68 and SM539, and both in Boom Clay and in FoCa-clay. In FoCa-clay at high density with glass frit, the dissolution rates, based on glass mass losses, after 8 months at 30°C are ∼ 0.001 g.m−2.day−1 (SM539) and ∼0.005 g.m−2.day−1 (SON68). Because the experiments performed in Boom Clay and FoCa-clay with glass frit simulate realistic conditions (high clay density, low temperature), they can be used to estimate the maximum glass dissolution rate in a (Boom) clay repository. The corresponding minimum lifetime of a glass canister, calculated with the SCK·CEN code for lifetime predictions, is of the order of 105 to 106 years, if we neglect the internal glass surface area (due to cracking). In more diluted clay suspensions with glass frit, the glass dissolution rate is 10−4 to 10−5 g.m−2.day−1 or even zero. This would correspond to a lifetime of >>106 years. So far, there is no indication that the addition of glass frit leads to secondary phase formation at low temperature (30–40°C). Leach experiments with doped glasses SON68 and SM539 suggest that the maximum concentrations of most critical radionuclides in near field conditions are lower than the best estimate solubilities used for performance assessment studies in Boom Clay. For Se, relatively high concentrations were measured, though. The research programme for the underground laboratory is not discussed.

A Study on the Vitrification Tests of the Low Level Radioactive Wastes Using Plasma Arc Melter System

2004 ◽  
Author(s):  
Boo Ho Yoon ◽  
Jae Hak Cho ◽  
Sang Chul Lee ◽  
Dong Woo Kang ◽  
Yong Joon Choi ◽  
...  
Keyword(s):  
Compressive Strength ◽  
Nuclear Power ◽  
Power Plants ◽  
Radioactive Wastes ◽  
Plasma Arc ◽  
Micro Hardness ◽  
Radioactive Materials ◽  
Low Level ◽  
Glass Density ◽  
Glass Formulation

For the research on the vitrification of the low-level radioactive wastes (LLRW) produced in nuclear power plants, one pilot plant with plasma arc melter system was built and several tests were done on it. Some surrogate wastes, which were spiked with several materials and were made very similar to the real LLRW, were used for these tests. For the vitrification of the surrogate wastes, the surrogate wastes were classified into the combustible, the non-combustible and the resin. Then each waste was spiked with special materials and was melted in separate. Off-gases produced in each test were picked up and analyzed. Real radioactive materials cesium (Cs) and cobalt (Co) were spiked in each wastes. Data gained from the final glass formulation were follows. Glass density is 2.42 ∼ 2.95(g/cm3), the compressive strength is 30 ∼ 175 Mpa, micro hardness is 5.5 ∼ 5.8 Gpa. The leaching ratio for Co is 1.27×10−4 ∼ 1.08×10−3 (10mL/g) and that for Cs is 2.46×10−3 ∼ 3.23×10−2 (10mL/g). The leaching speed for Co is 4.14×10−7 ∼ 5.53×10−6 (g/m2) and that for Cs is 4.58×10−5 ∼ 3.87×10−4 (g/m2). In off-gas, dioxin & furan is 0.016 mano gram on the average, CO is about 20 ppm, NO2 is about 15 ppm and SO2 is about 15 ppm.

scholarly journals High Waste Loading Glass Formulations for Hanford High-Aluminum High-Level Waste Streams

2011 ◽  
Author(s):  
Albert A. Kruger
Keyword(s):  
Previous Experience ◽  
High Level Waste ◽  
Waste Streams ◽  
Testing Program ◽  
Glass Formulation ◽  
Waste Loading ◽  
Production Requirement ◽  
High Level ◽  
Glass Compositions ◽  
High Aluminum

The current estimates and glass formulation efforts have been conservative in terms of achievable waste loadings. These formulations have been specified to ensure that the glasses are homogenous, contain essentially no crystalline phases, are processable in joule-heated, ceramic-lined melters and meet WTP Contract terms. The WTP’s overall mission will require the immobilization of tank waste compositions that are dominated by mixtures of aluminum (Al), chromium (Cr), bismuth (Bi), iron (Fe), phosphorous (P), zirconium (Zr), and sulfur (S) compounds as waste-limiting components. Glass compositions for these waste mixtures have been developed based upon previous experience and current glass property models. Recently, DOE has initiated a testing program to develop and characterize HLW glasses with higher waste loadings. Results of this work have demonstrated the feasibility of increases in waste loading from about 25 wt% to 33–50 wt% (based on oxide loading) in the glass depending on the waste stream. It is expected that these higher waste loading glasses will reduce the HLW canister production requirement by about 25% or more.

The effect of the conductive walls of the cooking furnace of an electric furnace on the distribution of energy flows

2020 ◽  
pp. 13-18
Author(s):  
N. N. Shustrov ◽  
V. G. Puzach ◽  
S. A. Bezenkov
Keyword(s):  
Glass Melting ◽  
Melting Furnace ◽  
Melting Process ◽  
Power Lines ◽  
Glass Mass ◽  
Thermal Processes ◽  
Industrial Furnace ◽  
Glass Melting Furnace ◽  
Energy Flows ◽  
Electric Glass

A method for modeling the electric glass melting process, which allows obtaining information about the unity of electric and thermal processes in the glass mass in an electric glass melting furnace has been developed. The furnace’s cooking pool is made of conductive chromoxide. The work was carried out using modeling on the EGDA integrator, as a result of which two versions of experimental electric furnaces with different directions of power lines and a pilot industrial furnace with a capacity of 7 tons per day for melting E glass, widely used in the manufacture of fiberglass, were built.

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