Borosilicate Glass Corrosion in the Presence of Steel Corrosion Products

1986 ◽  
Vol 84 ◽  
Author(s):  
G. Bart ◽  
H.U. Zwicky ◽  
E.T. Aerne ◽  
TH. Graber ◽  
D. Z'berg ◽  
...  
Keyword(s):  
Surface Area ◽  
Secondary Ion Mass Spectrometry ◽  
Corrosion Behaviour ◽  
Volume Ratio ◽  
Steel Corrosion ◽  
Sample Surface ◽  
Corrosion Products ◽  
High Level Waste ◽  
Glass Corrosion ◽  
High Level

AbstractSince 1982, the corrosion behaviour of radioactive high level waste glass and of inactive glasses of the same composition has been studied in the framework of a Japanese-Swedish-Swiss (JSS) project. In addition to granite and backfilling material, the influence of steel corrosion products on glass corrosion has been investigated in experiments of up to one year at 90°C with a sample surface area to leachant volume ratio of 10 m−1. Leachant and steel corrosion products were separated from each other by filtration and analyzed by atomic absorption spectroscopy and γ-spectroscopy. The glass corrosion layers were characterized by optical and scanning electron microscopy and by secondary ion mass spectrometry.It could be shown, that glass corrosion is enhanced by steel corrosion products. The quantity of corroded glass seems to be dependent on the surface area and not on the total amount of steel corrosion products in the system, suggesting a mechanism controlled by silica sorption on the steel corrosion product. If lead oxide is added to the system, glass corrosion is almost to- tally suppressed.

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.

Chemical Durability of High Burnup Lwr-Spent Fuel in Concentrated Salt Solutions

1993 ◽  
Vol 333 ◽  
Author(s):  
A. Loida ◽  
B. Grambow ◽  
P. Dressier ◽  
K. Friese ◽  
H. Geckeis ◽  
...  
Keyword(s):  
Surface Area ◽  
Volume Ratio ◽  
Sample Surface ◽  
Solution Concentration ◽  
Reaction Rates ◽  
Spent Fuel ◽  
Intrinsic Dissolution ◽  
Fine Grained ◽  
High Burnup ◽  
Saturation Effects

ABSTRACTHigh-burnup (<50 MWd/kgU) spent fuel samples of various sizes were exposed to NaCl solutions under static, anaerobic and reducing conditions. The accumulated corrosion time was about 200 days. Gas phase and leach solutions were analyzed. By dissolving mm sized fragments in large volumes of solution, saturation effects were avoided and upper limits for intrinsic dissolution rates of about 5-20 mg/(m2d) were measured. Surface area normalized reaction rates were significantly lower when using fine grained fuel powder (estimated sample surface area to solution volume ratio S/V ca. 3000 m-1), indicating saturation effects. The maximum concentrations of Pu and Am in the tests are close to reported solubility limited concentrations in pure 5m NaCl solutions in the absence of radiolysis effects. The presence of iron effectively reduces the solution concentration of all measured radionuclides (except Cs).

scholarly journals Analysis of Short-Term Steel Corrosion Products Formed in Tropical Marine Environments of Panama

2012 ◽  
Vol 2012 ◽  
pp. 1-11 ◽  
Author(s):  
Juan A. Jaén ◽  
Josefina Iglesias ◽  
Cecilio Hernández
Keyword(s):  
Corrosion Behaviour ◽  
Low Carbon Steel ◽  
Steel Corrosion ◽  
Corrosion Products ◽  
Urban Site ◽  
Low Carbon ◽  
Short Term ◽  
The Pacific ◽  
The Pacific Ocean ◽  
Time Of Wetness

A low-carbon steel A-36 and two conventional weathering steels A-588 and COR-420 exposed at four atmospheric test stations located in (i) Tocumen, an urban site near the Pacific Ocean, (ii) Sherman-Open, (iii) Sherman-Coastal, and (iv) Sherman-Breakwater on the Caribbean coast of Panama. Kinetics of the short-term atmospheric corrosion process and the relationship with exposure time and environmental characteristics of each site were investigated. The atmospheric exposure conditions, particularly the time of wetness, deposition of chloride, and the washing effect of contaminants on the metal surface by rain are of upmost importance in determining the corrosion behaviour and composition of rust. The corrosion products were mainly identified using room temperature and low temperature (80 K) Mössbauer spectroscopy, FTIR, and X-ray powder diffraction. In all samples,γ-FeOOH andα-FeOOH were the main constituents. Maghemite (γ-Fe2O3), magnetite (Fe3O4), and Akaganeite (β-FeOOH) were also identified.

Phases Formation and Elements Partitioning in the CaO-Gd2O3(UO2)-MnO-TiO2 System: Application to Rare Earth - Actinide Waste Immobilization

2002 ◽  
Vol 757 ◽  
Author(s):  
Olga I. Kirjanova ◽  
Sergey V. Stefanovsky ◽  
Sergey V. Yudintsev
Keyword(s):  
Rare Earth ◽  
Rare Earths ◽  
Corrosion Products ◽  
High Level Waste ◽  
Major Phase ◽  
Reducing Conditions ◽  
Transmission Electron ◽  
Unit Cells ◽  
Coupled Substitution ◽  
High Level

ABSTRACTCeramics within the compositional series Ca4-xGdxMn2Ti7O20+x/2 (x = 0, 1, 2, 3, 4) and a sample with Ca2U2Ti7O20 formulation were studied as promising matrices for immobilization of rare earth (RE) and actinide (An) constituents of high level waste (HLW). The samples were prepared by cold pressing of oxide mixtures in pellets at 200 MPa followed by their sintering at 1400 °C or melting at 1500 °C and examined with X-ray diffraction, scanning and transmission electron microscopy. At x=0 and x=1 a perovskite – pyrophanite assemblage occurred. The sample with x=2 consisted of murataite and perovskite. Murataite was a major phase in the sample with x=3 (pyrochlore and perovskite were minor phases) and the only phase in the sample with x=4 prepared under oxidizing conditions (in air). The latter was composed of two murataite varieties with seven- and five-fold fluorite unit cells. The sample with the same formulation but synthesized under reducing conditions contained pyrochlore as an extra phase. Coupled substitution 2 Gd3+ = Ca2+ + U4+ resulted in formation of pyrochlore as the major phase. Mu-rataite and perovskite are considered as the host phases for rare earths and actinides mainly trivalent, including Pu(III), Am(III), and Cm(III), and corrosion products (Mn, Fe, Al) whereas pyrochlore is the host phase for rare earths and tetravalent actinides (U(IV), Np(IV), Pu(IV)). This makes the system of calcium, gadolinium, manganese, and titanium oxides prospective for immobilization of RE – An fraction of HLW containing minor corrosion products (iron group elements).

Formation of secondary phases after long-term corrosion of simulated HLW glass in brine solutions at 190 °C

2002 ◽  
Vol 90 (9-11) ◽  
Author(s):  
P. Zimmer ◽  
E. Bohnert ◽  
Dirk Bosbach ◽  
Jae-Il Kim ◽  
E. Althaus
Keyword(s):  
Rare Earth ◽  
Rare Earth Elements ◽  
Glass Powder ◽  
High Level Waste ◽  
Secondary Phases ◽  
Batch Experiments ◽  
Salt Solutions ◽  
Glass Corrosion ◽  
High Level

SummaryThe behavior of rare earth elements (REE) as chemical analogues for actinides during glass corrosion was studied with static long-term batch experiments (7.5 years) at 190 °C. Corrosion tests were carried out using a simulated inactive high level waste (HLW) glass powder. Two different highly concentrated salt solutions (NaCl-rich and MgCl

The Long-Term Corrosion and Modelling of Two Simulated Belgian Reference High-Level Waste Glasses

1987 ◽  
Vol 112 ◽  
Author(s):  
P. Van Iseghem ◽  
B. Grambow
Keyword(s):  
Corrosion Behaviour ◽  
Stable Condition ◽  
High Level Waste ◽  
Forward Rate ◽  
Borosilicate Glasses ◽  
Al Content ◽  
Rate Of Dissolution ◽  
High Level ◽  
High Al Content

AbstractThe corrosion behaviour in distilled water of two simulated candidate high level waste borosilicate glasses (SAN602519L3C2 and SM58LW11) his been investigated at 90°C for different SA/V condition's 10, 100, 7800 m−1). The experimental data were modelled using the PHREEQE and GLASSOL computer codes. The model is quite successful for describing the corrosion behaviour, using experimentally derived values for the forward rate, silica saturation and the final rate. GWss SAN60 is more stable than glass SM58 at SA/V values of 10 and 100 m−1, but in the long term the relative performance is inverse. Indeed, the high Al content of SAN60 induces the creation of analcime crystals after SiO2 has reached its saturation concentration in solution, which cause an enhancement of the final rate of dissolution of the glass; for SM58 on the contrary the SiO2 solution is a stable condition.

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