scholarly journals Preparation and Study of Corrosion Behavior of Some Simulated Radioactive Waste Glasses

2019 ◽  
Vol 16 (3) ◽  
pp. 271-279
Author(s):  
Patit Paban Malik
Keyword(s):  
Radioactive Waste ◽  
Ground Water ◽  
Corrosion Behavior ◽  
Iron Phosphate ◽  
Leaching Behavior ◽  
Time Intervals ◽  
Safe Environment ◽  
Leach Rate ◽  
Weight Losses ◽  
Leachate Solution

To safe environment from radioactive waste it is important to fix them as radioactive waste glasses. The corrosion behavior of radioactive waste glasses in water is significantly important. Radionuclides return to the biosphere by means of leaching from waste form into ground water. Finally the ground water containing the radionuclide are transported to the surface. In this study, the preparation, characterization and leaching behavior of some borosilicate (BS) and lead iron phosphate (LIP) of different chemical composition doped with simulated nuclear waste oxide were investigated. We measured the pH found to be in the range from 6.78 up to 7.79 of the leachate solution at normal temperature and at varying time intervals. Leaching study of these glasses were conducted with the help of Soxhlet distillation apparatus with distilled water upto 24 hours and for BS9 - BS12 upto 100 hours duration. Weight losses were are measured with respect to time of leaching. Leach rate of some borosilicate glass samples loaded with uranium are calculated from surface area measurements. The results are reported in the range 1.34x10-4 g.m-2.hr-1 and 6.26 x 10-4 g.m-2.hr-1 respectively at 90°C.

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.

Characterization and Leaching Behavior of Plutonium-Bearing Synroc-C

1996 ◽  
Vol 465 ◽  
Author(s):  
Katherine L. Smith ◽  
Gregory R. Lumpkin ◽  
Mark G. Blackford ◽  
Michelle Hambley ◽  
R. Arthur Day ◽  
...  
Keyword(s):  
Vessel Wall ◽  
Starting Material ◽  
Secondary Phases ◽  
Leaching Behavior ◽  
Leach Rate

ABSTRACTSynroc-C containing 10wt% simulated PW-4b-D HLW including 0.62 wt% 239Pu was subjected to MCC-1 type leach tests at 70°C in deionised water, silicate and carbonate leachates for 53 d and deionised water for 2472 d. The normalised total (i.e. unfiltered leachate + vessel wall) Pu leach rates in deionised water, silicate and carbonate leachates for periods up to 53 d were found to be of the order of 10-5, 10-4 and 10-4 g m-2 d-1 respectively. After 2472 d, the differential, normalised, Pu leach rate in deionised water dropped to ∼5 × 10-6 (total) and ∼5 × 10-8 (solution - after filtration through a 1000NMW filter) g m-2 d-1. SEM and AEM were used to characterise our starting material and investigate the secondary phases on the surfaces of leached Synroc-C discs. Calculated and measured normalised Pu leach rates are compared and the partitioning of Pu between zirconolite and perovskite is discussed.

XAFS analysis of ruthenium in simulated iron phosphate radioactive waste glass

2021 ◽  
Vol 551 ◽  
pp. 120393
Author(s):  
Yoshihiro Okamoto ◽  
Hidekazu Kobayashi ◽  
Hideaki Shiwaku ◽  
Ken-ichi Sasage ◽  
Kiyoshi Hatakeyama ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Iron Phosphate ◽  
Waste Glass

Atmospheric Corrosion in Marine Environments

CORROSION ◽  
1978 ◽  
Vol 34 (12) ◽  
pp. 433-437 ◽  
Author(s):  
R. A. LEGAULT ◽  
V. P. PEARSON
Keyword(s):  
Corrosion Behavior ◽  
Atmospheric Corrosion ◽  
Low Alloy Steels ◽  
Marine Environments ◽  
Weight Losses ◽  
Alloy Steels

Abstract It has been demonstrated that the natural atmospheric corrosion behavior of low alloy steels in marine environments can be accurately described by an equation of the form: ΔW = KtN. With this relationship, reliable predictions of long term weight losses can be made from as few as two sets of determinations obtained in relatively short exposures. The reliability of this relationship has also been established for galvanized and aluminized steels.

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