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CHayashi, Maki*; Satake, Kenji*; Sasamoto, Hiroshi
JAEA-Data/Code 2006-012, 25 Pages, 2006/03
JAEA-Data-Code-2006-012.pdf:2.2MB
An international interlaboratory study (ILS) was coordinated by Argonne National Laboratory (ANL) to evaluate the precision and bias of a single-pass flow-through (SPFT) test method that can be used to measure the forward dissolution rate of borosilicate glass. In this report we present the results of tests conducted at 70C using the LRM glass prepared by ANL. Based on measurements of the concentrations of glass components (i.e., Si, B and Na) in effuluent solutions and the solution flow rate, glass dissolution rates were calculated under the steady-state concentrations of glass components. The rates in the absence of glass components were estimated by extrapolation of the experimental results to zero concentration of glass components. Results show that the average pH of effuluent solutions was 11.68
0.23 (0.23 refers to standard deviation) at room temperature (21.784.03C, 4.03 means standard deviation). The estimated dissolution rate of LRM glass, based on variations in Si, B and Na concentrations in the absence of solution-feedback effects, is 2.11, 1.99 and 1.93 (g/m
d), respectively. The reliability of these estimates is questionable, however, due to considerable scatter in the aqueous concentration data. Based on these results, it is suggested that carefully controlled and constant flow rates are required to obtain reliable data using the SPFT test method.
Hayashi, Maki*; Satake, Kenji*; Yoshikawa, Hideki; Yui, Mikazu
JNC TN8400 2005-008, 30 Pages, 2005/04
JNC-TN8400-2005-008.pdf:32.41MB
The dissolution rate of radionuclide from radioactive waste (HLW) glass is one of the important parameters for the safety assessment of the geological disposal system. A lot of information on the dissolution behavior of the glass are open to the public and have useful information to understand the essential characteristic of the glass under various conditions. We collected information on the dissolution behavior of the glass (Glass, Experimental Type, Solution, Experimental Conditions, Experimental Results, Reference) from Scientific Basis for Nuclear Waste management published by Materials Research Society (MRS). This system contains 846 data now. This database is supported by Windows Me / Access2002 to search of data, reference document, and graphs.
; Kamei, Gento
JNC TN8400 2002-003, 25 Pages, 2002/03
JNC-TN8400-2002-003.pdf:5.06MB
The influence of carbon steel and its corrosion products on leaching of elements from simulated high level radioactive waste glass (P0798) has been investigated in batch-type experiments of up to one year at 253C under argon atmosphere (
1 ppm oxygen) with a surface area of the glass sample to leachant volume ratios of 10, 100 and 1000m
. For each series, a polished glass cube or glass particles were immersed in double distilled deoxidized water with powder of carbon steel or of magnetite, as an assumed carbon steel corrosion product, in the ratio of 10 gram carbon steel (or magnetite) to 1 litter of water. Normalized mass losses of Si, B, Na and Cs in the systems of glass-carbon steel-water and of glass-magnetite-water apparently increased compared with those in the glass-water system. The glass dissolution could be accelerated by increasing hydroxyl ion resulting from hydrolysis of carbon steel or of magnetite. The pH values of leachate become eventually almost constant and it indicates that a steady state has been attained between these hydroxyl ion releases and its consumption, which is a disruption process of siloxane bond by hydroxyl ion in solution. The influence of carbon steel and its corrosion products on leaching of elements from the waste glass can be predominantly attributed to a pH effect in this experiment. The increase of glass corrosion rate, however, could be assessed within one order as an influence of the existence of carbon steel and/or its corrosion products.
Hayashi, Maki*; Satake, Kenji*; Sasamoto, Hiroshi; Yoshikawa, Hideki; Yui, Mikazu
no journal, ,
In the analysis of radionuclides migration in the performance assessment of geological disposal system, the release of radionuclides from vitrified glass is considered as the source-term for radionuclides migration, and model development and quantitative assessment of glass dissolution are necessary for the analysis. For a realistic assessment of radionuclides release from the vitrified waste glass, further research to improve understanding based on the scientific basis and development of robust glass dissolution model are important. As one of the tool to reflect these researches, we have been developing the Glass Dissolution Rate Database. This database has information on the dissolution behavior of glass. We researched the documents about the leaching tests of HLW glass, and registered the data of normalized elemental mass loss from HLW glass with experimental conditions. At present the prototype database has been developed using Microsoft Access.