Static Leaching of Fully Radioactive Waste Glass at 90°C in the Presence of Bentonite, Granite, and Stainless Steel Corrosion Products

1985 ◽  
Vol 50 ◽  
Author(s):  
Hans-Peter Hermansson ◽  
Inga-Kari Björner ◽  
Hilbert Christensen ◽  
Toshiaki Ohe ◽  
Lars Werme
Keyword(s):  
Stainless Steel ◽  
Radioactive Waste ◽  
Steel Corrosion ◽  
Corrosion Products ◽  
Leach Rate ◽  
Compacted Bentonite ◽  
Infrared Reflection ◽  
Leaching Experiments ◽  
Leaching Behaviour ◽  
Glass Leaching

AbstractThe results from the JSS phase II static glass leaching experiments are presented. The experiments have been performed in the presence of bentonite, granite and stainless steel corrosion products at 90°C for 28 days. The leaching behaviour of Cs has been analysed using gamma-spectrometry. The surface of the leached glass samples has been analysed by infrared reflection spectrometry.The presence of uncompacted bentonite seems to have a very small, increasing, effect on the leach rate of the glass compared to when no bentonite is present. In the presence of compacted bentonite, a lower leach rate has beep founy than in the prgsencelof uncompacted bentonite. (For Cs 0.3 g × m−2 × d−1 and 0.7 g × m−2 × d−1 respectively.) The addition of stainless steel corrosion products seems to have a slightly increasing effect on the leach rate in the presence of compacted bentonite. The beneficial effect of granite on the leach rate seems to be overshadowed by the presence of uncompacted bentonite.

Leaching of Am-241 from a Radioactive Waste Glass Corroded in the Presence of Stainless Steel Corrosion Products and/or Bentonite

1987 ◽  
Vol 112 ◽  
Author(s):  
Masaki Tsukamoto ◽  
Inga-Kari Björner ◽  
Hilbert Christensen ◽  
Hans-Peter Hermansson ◽  
Lars Werme
Keyword(s):  
Stainless Steel ◽  
Radioactive Waste ◽  
Mass Loss ◽  
Total Mass ◽  
Corrosion Behaviour ◽  
Steel Corrosion ◽  
Waste Glass ◽  
Corrosion Products ◽  
Total Mass Loss ◽  
Elemental Mass

AbstractThe release of Am-241 during corrosion of the radioactive waste glass, JSS-A, has been studied in the presence of corrosion products and/or uncom-pacted bentonite. The corrosion behaviour of Am-241 has been analyzed using gamma spectrometry. Adsorption of Am-241 on bentonite is observed in all cases. The contents of Am-241 in centrifuged leachates are in most cases less than 1/100 of total values. The normalized elemental mass loss of Am increases initially with corrosion time, and the values in the presence of bentonite and corrosion products are larger than those in the presence of bentonite alone. This tendency is in agreement with results previously found for other elements. The release of Am is low, only about 10–20 % of the corresponding total mass loss.

Characterization of Solidified Radioactive Waste Due to the Incorporation of High-and Low-Density Polyethylene Granules and Titanium Dioxide in Mortar Matrices

1996 ◽  
Vol 465 ◽  
Author(s):  
Aleksandar Perić
Keyword(s):  
Titanium Dioxide ◽  
Radioactive Waste ◽  
Average Diameter ◽  
Weight Percent ◽  
Low Density Polyethylene ◽  
Accelerated Ageing ◽  
Low Density ◽  
Leach Rate ◽  
Leaching Experiments ◽  
Mortar Matrix

ABSTRACTThe rutile form of titanium dioxide (TiO2) and granules of high density polyethylene (PEHD) and low density polyethylene (PELD) were used to prepare mortar matrices for immobilization of radioactive waste materials containing ‘137Cs. PELD,PEHD and TiO2 were added to mortar matrix preparations with the objective of improving physico-chemical characteristics of the radwaste-mortar matrix mixtures, in particular the leach-rate of the immobilized radionuclide. The diameters of the PELD and PEHD used varied from 0.2 to 2.0 mm. One type of PELD and two types of PEHD were used to replace 50 weight percent of stone granules, average diameter of 2 mm, normally used in the matrix, in order to decrease the porosity and density of the mortar matrix and to avoid segregation of the stone particles at the bottom of the immobilized radioactive waste cylindrical form. TiO2 was also added to the mortar formulation, replacing 5 and 8 weight percent of the total cement weight, for each PEHD and PELD formulation. Cured samples were investigated under temperature stress conditions, where the temperature extremes were: Tmill = -20°C,Tmax= +70°C. Samples were periodically immersed in distilled water at the ambient room temperature, after each freezing and heating treatment. Results of accelerated leaching experiments for these samples and samples prepared exclusively with polyethylenes replacing 100 percents of the stone granules and TiO2, treated in nonaccelerated leaching experiments, were compared. Even using an accelerated ageing leach test that overestimates 137Cs leach rates, it can be deduced, that radionuclide leach rates from the radioactive waste mortar mixture forms were improved. Leach rates decreased from 5 percent, for the material prepared with stone aggregate, to 3.1 to 4.0 percent, for the materials prepared solely with PEHD, PELD or TiO2, and to about 3 percents for all six types of the TiO2-PEHD and TiO2-PELD mixtures tested.

The Leaching Behavior of Bituminized Radioactive Waste in the Geologic Disposal Conditions of the Boom Clay Formation

1997 ◽  
Vol 506 ◽  
Author(s):  
A. Sneyers ◽  
P. Van Iseghem
Keyword(s):  
Radioactive Waste ◽  
Crack Formation ◽  
Soluble Salts ◽  
Leaching Behavior ◽  
Boom Clay ◽  
Leach Rate ◽  
Diffusion Controlled ◽  
Geologic Disposal ◽  
Leaching Behaviour ◽  
Clay Formation

ABSTRACTAs part of the evaluation of the safety of geologic disposal, the leaching behaviour of two types of bituminized radioactive waste (Eurobitum and CEA bitumen) has been studied as a function of temperature, pressure, leachant composition and bitumen matrix type. Inactive and active bitumen samples were brought into contact with two test media, simulating the geologic disposal environment of the Boom clay formation. At contact with these media, the samples swelled and soluble salts and radionucides were leached. It was found that the leach rate is influenced by temperature, the leachant composition, and the physical characteristics of the bitumen matrix. The release of nitrate is interpreted as a diffusion controlled process, which can however be disturbed by crack formation. The leaching of 60Co, 90Sr, and total β is diffusion controlled. Low leach rates were measured for Pu and Am: the release of Pu and Am is limited by their solubility in the leachant. Pu and Am are preferentially sorbed to the Boom clay, the test container or the bitumen. The leached mobile Pu and Am concentrations are of the order of 10−10 to 1013 M at 23°C. The results of this study suggest that the integrity of bituminized waste packages is seriously affected due to the leaching of soluble salts: a full-size 220 litre Eurobitum drum is predicted to be depleted in NaNO3 in less than 20,000 years.

Mouse inflammatory response to stainless steel corrosion products

1994 ◽  
Vol 5 (9-10) ◽  
pp. 596-600 ◽  
Author(s):  
R. B. Tracana ◽  
J. P. Sousa ◽  
G. S. Carvalho
Keyword(s):  
Stainless Steel ◽  
Inflammatory Response ◽  
Steel Corrosion ◽  
Corrosion Products

Stainless steel corrosion products cause alterations on mouse spleen cellular populations

1995 ◽  
Vol 6 (1) ◽  
pp. 56-61 ◽  
Author(s):  
R. B. Tracana ◽  
M. L. Pereira ◽  
A. M. Abreu ◽  
J. P. Sousa ◽  
G. S. Carvalho
Keyword(s):  
Stainless Steel ◽  
Steel Corrosion ◽  
Corrosion Products ◽  
Mouse Spleen

Effects of Recrystallization on Time Variant Sorption of Radionuclides onto Steel Corrosion Products

1993 ◽  
Vol 333 ◽  
Author(s):  
Robert W. Smith ◽  
John C. Walton ◽  
Masudur Rahman
Keyword(s):  
Radioactive Waste ◽  
Surface Area ◽  
Corrosion Product ◽  
Waste Disposal ◽  
Complex Function ◽  
Steel Corrosion ◽  
Corrosion Products ◽  
Radioactive Waste Disposal ◽  
Geochemical Environment ◽  
The Impact

ABSTRACTCorrosion products resulting from the oxidation of steel containers and iron-containing waste can alter the local geochemical environment in radioactive waste disposal vaults and trenches. In addition, corrosion products can enhance the retention of radionuclides by providing a highly sorptive media. Initial hydrous corrosion products are poorly crystalline with large surface area, high sorption capacity, and large Kds. Over time, corrosion products recrystallize by step-wise dehydration to phases with significantly smaller surface areas. The decreased surface area results in decreased sorption and the potential for remobilization of previously sorbed radionuclides. The impact of time-dependent variation in sorption on radionuclide transport is a complex function of the rate of recrystallization and the radionuclide half-life.A mathematical model has been developed, which coupling mass transport with corrosion product recrystallization and equilibrium sorption of radionuclides. The model is applied release of radionuclides with a range of half-lives (year to 100,000s of years) from radioactive waste disposal facilities to illustrate the significance of corrosion product recrystallization on release.

Protective postaction of inhibitor IFKhAN-92 for chromium-nickel stainless steel corrosion in hydrochloric acid

2019 ◽  
pp. 20-25
Author(s):  
Ya.G. Avdeev ◽  
◽  
Yu.B. Makarychev ◽  
D.S. Kuznetsov ◽  
L.P. Kazanskii ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Hydrochloric Acid ◽  
Steel Corrosion
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