TY - JOUR
T1 - Comparative study of hydrothermal stability experiments
T2 - Application to simulated nuclear waste forms
AU - Scheetz, Barry E.
AU - Phelps Freeborn, W.
AU - Komarneni, Sridhar
AU - Atkinson, Scott D.
AU - White, William B.
N1 - Funding Information:
Research supported in part by the U.S. Department of Energy under Contract E512/03400 with the Office of Nuclear Waste Isolation, Battelle Memorial Institute and in part by the U.S. Department of Energy through Rockwell Hanford operations under Contract No. 1 EY-77-C-06-1030. Reprints may be requested from the authors at Materials Research Laboratory, The Pennsylvania State University, University Park, PA 16802.
PY - 1981
Y1 - 1981
N2 - The hydrothermal dissolution behavior of two simulated nuclear waste forms, a borosilicate glass and a tailored ceramic, was investigated by three types of high pressure apparatus: sealed gold capsules in cold seal pressure vessels, a rocking autoclave apparatus, and a fluid injection, flow-through type apparatus. Saturation of the solutions was observed in both cold seal and rocking autoclave apparatus which provide information about limiting solubilities, solid reaction products, and kinetic data near saturation. The flow-through system provides kinetic data at high undersaturations and gives the hydrothermal dissolution rates that are most comparable to leach rates determined with atmospheric pressure measurements.
AB - The hydrothermal dissolution behavior of two simulated nuclear waste forms, a borosilicate glass and a tailored ceramic, was investigated by three types of high pressure apparatus: sealed gold capsules in cold seal pressure vessels, a rocking autoclave apparatus, and a fluid injection, flow-through type apparatus. Saturation of the solutions was observed in both cold seal and rocking autoclave apparatus which provide information about limiting solubilities, solid reaction products, and kinetic data near saturation. The flow-through system provides kinetic data at high undersaturations and gives the hydrothermal dissolution rates that are most comparable to leach rates determined with atmospheric pressure measurements.
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U2 - 10.1016/0191-815X(81)90020-6
DO - 10.1016/0191-815X(81)90020-6
M3 - Article
AN - SCOPUS:0019831969
SN - 0191-815X
VL - 2
SP - 229
EP - 236
JO - Nuclear and Chemical Waste Management
JF - Nuclear and Chemical Waste Management
IS - 3
ER -