Secondary Uranium Minerals on the Surface of Chernobyl
                        “Lava”

Burakov, Boris E.; Strykanova, E. E.; Anderson, Ε. B.

doi:10.1557/proc-465-1309

Cited by 77 publications

(63 citation statements)

References 3 publications

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“…Metastudtite formed on the surface of UO 2 under irradiation with a 4 He 2+ (alphaparticle) beam, and incorporated peroxide formed by alpha-radiolysis of water [64]. Studtite has also been found on nuclear material (''lava") following the Chernobyl Nuclear Plant accident [65].…”

Section: Uranyl Peroxidesmentioning

confidence: 99%

Review of uranyl mineral solubility measurements

Gorman‐Lewis

Burns

Fein

2008

The Journal of Chemical Thermodynamics

215

144

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Section: Uranyl Peroxidesmentioning

confidence: 99%

Review of uranyl mineral solubility measurements

Gorman‐Lewis

Burns

Fein

2008

The Journal of Chemical Thermodynamics

215

144

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“…Given the long history of nuclear operations and related waste disposal at the AEC/DOE complex, čejkaite or its trigonal polymorph may have been physically identified and 3.37 documented in old classified or unclassified reports. More recently, čejkaite has been identified as a secondary mineral at a uranium ore deposit in the Czech Republic (Ondruš et al 2003), and possibly as an alteration product of the silicate lava that solidified from the destruction of the Chernobyl reactor core (Burakov et al 1997). …”

Section: Comparison Of Leached and Unleached C-203 And C-204 Sludge Smentioning

confidence: 99%

Hanford Tanks 241-C-203 and 241 C 204: Residual Waste Contaminant Release Model and Supporting Data

Deutsch¹,

Krupka²,

Lindberg³

et al. 2007

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This report describes the development of release models for key contaminants that are present in residual sludge remaining after closure of Hanford Tanks 241-C-203 (C-203) and 241-C-204 (C-204). The release models were developed from data generated by laboratory characterization and testing of samples from these two tanks. Key results from this work are that future releases from the tanks of the primary contaminants of concern ( 99 Tc and 238 U) can be represented by relatively simple solubility relationships between infiltrating water and solid phases containing the contaminants. In addition, it was found that high percentages of 99 Tc in the sludges (20 wt% in C-203 and 75 wt% in C-204) are not readily water leachable, and, in fact, are very recalcitrant. This is similar to 99 Tc results found in related studies of sludges from Tank AY-102 (Lindberg and Deutsch 2003;Krupka et al. 2004). These release models are being developed to support the tank closure risk assessments performed by CH2M HILL Hanford Group, Inc., for the U.S. Department of Energy.The material used for testing consisted of sludge samples collected from the tanks in September 2003. Initial (Tier 1) testing of the sludges consisted of 1) fusion analysis and acid digestion to determine the total composition of the sludges and 2) water leaching to estimate the soluble portion of the solids. Based on the results of these tests, subsequent analyses were conducted (Tier 2). These included X-ray diffraction (XRD) measurements to identify crystalline solids and scanning electron microscopy/energy dispersive spectroscopy (SEM/EDS) analysis to provide a close-up view of the morphologies of the sludge material and identify the major constituents of individual minerals and amorphous solids. Periodic replenishment and selective extraction tests were also conducted during the Tier 2 tests to further evaluate water leachability and identify solid phases limiting the release of contaminants to solution. The test data were used to develop conceptual contaminant release models based on a series of solubility controls.The 99 Tc release model developed from the laboratory testing of C-203 and C-204 sludges is based on the concentrations and solubilities of technetium-bearing solids in contact with pore water migrating through the sludges. There are two stages of technetium release to solution: The 238 U release model for C-203 and C-204 sludges is based on the concentrations and solubilities of uranium-and sodium-bearing minerals in contact with pore water migrating through the sludges. There are three stages of uranium release to solution:1. Initially, soluble čejkaite [Na 4 (UO 2 )(CO 3 ) 3 ] and a sodium nitrate solid are present in the sludges at concentrations of 0.16 g U/g-sludge and 0.22 g NaNO 3 /g-sludge for C-203 and 0.068 g U/g-sludge and 0.04 g NaNO 3 /g-sludge for C-204. The common ion effect due to Na + limits the solubility of čejkaite to 0.19 g U/L until all the NaNO 3 is dissolved. The solubility of NaNO 3 is constant at 629 g/L.2. After all the ...

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“…[16] Behaviour of uranium in solid solution, especially the stability of Na 4 [UO 2 (CO 3 ) 3 ], was presented by Rafalskii. [17] Burakov et al [18] reported on a number of minerals including Na 4 [UO 2 (CO 3 ) 3 ], studtite (UO 4 · 4H 2 O), epiianthinite (UO 3 · 2H 2 O), rutherfordine (UO 2 CO 3 , Na 3 H(CO 3 ) 2 · 2H 2 O) and Na 2 CO 3 ·H 2 O as yellow products of alteration that stain the surface of Chernobyl 'lava'. Catalano and Brown [19] analysed syntheticčejkaite by EX-AFS spectroscopy.…”

Section: Introductionmentioning

confidence: 99%

Raman spectroscopic study of the uranyl carbonate mineral čejkaite and its comparison with synthetic trigonal Na₄[UO₂(CO₃)₃]

Čejka

Sejkora

Plášil

et al. 2009

J Raman Spectroscopy

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Raman and infrared spectroscopies were used to characterise two samples of triclinicčejkaite Na 4 [UO 2 (CO 3 ) 3 ] and its synthetic trigonal analogue. The ν 3 (UO 2 ) 2+ mode is not Raman active, whereas both the ν 3 and ν 1 (UO 2 ) 2+ modes are infrared active. U-O bond lengths in uranyls were calculated from the spectra obtained and compared with bond lengths derived from crystal structure analyses. From the higher number of bands related to the uranyl and carbonate vibrations, the presence of symmetrically distinct (UO 2 ) 2+ and (CO 3 ) 2− units in both structures is proposed.

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Secondary Uranium Minerals on the Surface of Chernobyl “Lava”

Cited by 77 publications

References 3 publications

Review of uranyl mineral solubility measurements

Review of uranyl mineral solubility measurements

Hanford Tanks 241-C-203 and 241 C 204: Residual Waste Contaminant Release Model and Supporting Data

Raman spectroscopic study of the uranyl carbonate mineral čejkaite and its comparison with synthetic trigonal Na₄[UO₂(CO₃)₃]

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Secondary Uranium Minerals on the Surface of Chernobyl “Lava”

Cited by 77 publications

References 3 publications

Review of uranyl mineral solubility measurements

Review of uranyl mineral solubility measurements

Hanford Tanks 241-C-203 and 241 C 204: Residual Waste Contaminant Release Model and Supporting Data

Raman spectroscopic study of the uranyl carbonate mineral čejkaite and its comparison with synthetic trigonal Na4[UO2(CO3)3]

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Product

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Raman spectroscopic study of the uranyl carbonate mineral čejkaite and its comparison with synthetic trigonal Na₄[UO₂(CO₃)₃]