Aqueous corrosion of natural and nuclear waste glasses II. Mechanisms of vapor hydration of nuclear waste glasses

Abrajano, T.A.; Bates, J. K.; Mazer, J.J.

doi:10.1016/0022-3093(89)90297-4

Cited by 73 publications

(40 citation statements)

References 24 publications

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“…Abrajano et al (1989) measured glass dissolution rates at various relative humidities and found that glass dissolution proceeds above 70 percent relative humidity but is absent or very slow below this value. If it is assumed that the pressures in the cavity are primarily hydrostatic in nature, and that the maximum hydrostatic pressure is observed under ambient groundwater conditions, a calculation can be made of the relative humidity in the glass zone above the boiling temperature of water under hydrostatic conditions.…”

Section: Resultsmentioning

confidence: 99%

Modeling of Groundwater Flow and Radionuclide Transport at the Climax Mine sub-CAU, Nevada Test Site

Pohlmann¹,

Ye²,

Reeves³

et al. 2007

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Section: Resultsmentioning

confidence: 99%

Modeling of Groundwater Flow and Radionuclide Transport at the Climax Mine sub-CAU, Nevada Test Site

Pohlmann¹,

Ye²,

Reeves³

et al. 2007

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“…The elevated temperatures used in these tests (150 to 200°C) exceed those that may be expected for glass waste in an actual repository. These high temperatures were used to accelerate glass reactions based on the premise that the glass reaction mechanism in water vapor remains unchanged within the range of 70 to 240°C [8].…”

Section: Methodsmentioning

confidence: 99%

Effects of Radiation Exposure on Glass Alteration in a Steam Environment

1992

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Several Savannah River Plant (SRL) glass compositions were reacted in steam at temperatures of 150 to 200°C. Half of the tests utilized actinide-doped monoliths and were exposed to an external ionizing gamma source, while the remainder were doped only with U and reacted without gamma exposure. All glass samples readily reacted to form secondary mineral phases within the first week of testing. An in situ layer of smectite initially developed on nonirradiated SRL 202 glass test samples. After 21 days, a thin layer of illite was precipitated from solution onto the smectite layer. A number of alteration products including zeolite, Casilicate, and alkali or alkaline earth uranyl silicate phases were also distributed over most sample surfaces. In the irradiated SRL 202 glass tests, up to three layers enveloped rounded, and sometimes fractured, glass cores. After 35 to 56 days these remnant cores were replaced by a mottled or banded Fe- and Si-rich material. The formation of some secondary mineral phases also has been accelerated in the irradiated tests, and in some instances, the irradiated environment may have led to the precipitation of a different suite of minerals. The alteration layer(s) developed at rates of 2.3 and 32 μm/day for the nonirradiated and irradiated SRL 202 glasses, respectively, indicating that layer development is accelerated by a factor of ∼10 to 15X due to radiation exposure under the test conditions.

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“…Observations that indicate water film growth on glass surfaces exposed in humid atmospheres, even to the point at which the films may flow and drip off, have been reported by other authors [6,7]. These observations can be explained by the fact that the water initially adsorbed on the glass surface can support ion exchange reactions that release sodium and other solutes which then decrease the water vapor pressure at the surface of the glass.…”

Section: Laboratory Testing and Validationof Wasteformradionuclide Rementioning

confidence: 59%

The Role of Laboratory Analog Experiments in Assessing the Performance of Waste Package Materials

Cunnane

Bates

1990

MRS Proc.

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DE91 006503There is an immediateneed to begin to validate models that car_'_2_/Iiggl used for assessing the performanceof waste package materials in an unsaturatedrepositoryenvironment. This paper examines available testing informationand testing approachesthat could supportvalidationof models for engineering:barriersystem (EBS) radionucliderelease. The content is presented in the contextof the general methodologythat has been proposed for validatingperformance assessmentmodels [I]. Available experimental observationsare used to test some of the EBS release rate modeling premises. These observationsinclude evidence of fluid film formation on waste glass surfaces in isothermalhumid environments,acceleratedwaste glass reaction rates under repositoryservice conditionsof large glass surfacearea 'towater volume ratio, and mobilizationof radionuclidesas solutesand colloids, lt is concludedthat some importantmodeling premisesmay not be consistentwith availableexperimentalinformation. However, it is also concluded that future laboratorytesting, which simulatesthe integratedwaste package system (i.e., laboratoryanalog testing),is needed to evaluate the significanceof these inconsistencies and to test the system level models. A small-scaleapparatuswhich was developed and tested to examine the feasibilityof laboratoryanalog testing for the unsaturatedYucca Mountain repositoryenvironment is described.

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Aqueous corrosion of natural and nuclear waste glasses II. Mechanisms of vapor hydration of nuclear waste glasses

Cited by 73 publications

References 24 publications

Modeling of Groundwater Flow and Radionuclide Transport at the Climax Mine sub-CAU, Nevada Test Site

Modeling of Groundwater Flow and Radionuclide Transport at the Climax Mine sub-CAU, Nevada Test Site

Effects of Radiation Exposure on Glass Alteration in a Steam Environment

The Role of Laboratory Analog Experiments in Assessing the Performance of Waste Package Materials

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