E 1.99:conf-841142-
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Environmental research on actinide elements |
1 |
E 1.99: conf-841157-1
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Source term development for tritium at the Sheffield disposal site |
1 |
E 1.99: conf-841157-2
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Leachability of decontamination reagents from cement waste forms |
1 |
E 1.99:conf-841157-4
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Radiation-induced compositional redistribution and local phase transformation in irradiated alloys |
1 |
E 1.99: conf-841157--6
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Corrosion behavior of carbon steels under tuff repository environmental conditions |
1 |
E 1.99: conf-841157--7
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Solubility limits on radionuclide dissolution |
1 |
E 1.99: conf-841157-8
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Irradiation-induced reduction of microcracking in zirconolite |
1 |
E 1.99:conf-841157--13
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Behavior of nuclear waste elements during hydrothermal alteration of glassy rhyolite in an active geothermal system Yellowstone National Park, Wyoming. |
1 |
E 1.99:conf-841157-14
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Functions of the Materials Review Board |
1 |
E 1.99:conf-841157--15
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Gamma irradiation in a saturated tuff environment |
1 |
E 1.99:conf-841157-16
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Extrapolation of nuclear waste glass aging |
1 |
E 1.99:conf-841157--17
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NNWSI waste form performance test development |
1 |
E 1.99:conf-841157-18
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Rapid increases in permeability and porosity of bentonite-sand mixtures due to alteration by water vapor |
1 |
E 1.99: conf-841157--25
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Hydrothermal interaction of Topopah Spring tuff with J-13 water as a function of temperature |
1 |
E 1.99: conf-841157-32
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Hot cell preparation of approved testing materials for the Materials Characterization Center |
1 |
E 1.99:conf-841157-39
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Basalt glass an analogue for the evaluation of the long-term stability of nuclear waste form borosilicate glasses. |
1 |
E 1.99: conf-841157-40
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Purpose of the Materials Characterization Center |
1 |
E 1.99: conf-841157-46
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Thermodynamically coupled mass transport processes in a saturated clay |
1 |
E 1.99:conf-841157-50
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Cleanout of waste storage tanks at Oak Ridge National Laboratory |
1 |
E 1.99: conf-841157-62
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Extension of the EQ3/6 computer codes to geochemical modeling of brines |
1 |