| Call Number (LC) | Title | Results |
|---|---|---|
| E 1.99:conf-910435-36 | Transportation capabilities of the existing cask fleet | 1 |
| E 1.99: conf-910435--37 | Fracture-lining minerals in the lower Topopah Spring Tuff at Yucca Mountain | 1 |
| E 1.99: conf-910435--39 | Degradation mode surveys of high performance candidate container materials | 1 |
| E 1.99: conf-910435--40 | Uncertainty analysis of preclosure accident doses for the Yucca Mountain repository | 1 |
| E 1.99: conf-910435--41 | Evaluation of storage/transportation options to support criteria development for the Phase I MRS (Monitored Retrievable Storage) | 1 |
| E 1.99: conf-910435--42 | Laboratory determined suction potential of Topopah Spring tuff at high temperatures | 1 |
| E 1.99: conf-910435--44 | Removal of dissolved and suspended radionuclides from Hanford Waste Vitrification Plant liquid wastes | 1 |
| E 1.99: conf-910435--45 |
The processing of simulated high-level radioactive waste sludges containing nitrites and mercury Radionuclide migration as a function of mineralogy |
2 |
| E 1.99: conf-910435--46 | The adoption of mechanized excavation techniques for the Superconducting Super Collider | 1 |
| E 1.99: conf-910435--47 | The constructive use of heat in an unsaturated tuff repository | 1 |
| E 1.99: conf-910435--49 | Potential ¹⁴CO₂ releases from spent fuel containers at Yucca Mountain | 1 |
| E 1.99: conf-910435--50 | Microwave measurements of the water content of bentonite | 1 |
| E 1.99: conf-910435--51 | Theory of matrix and fracture flow regimes in unsaturated, fractured porous media | 1 |
| E 1.99: conf-910435--52 | Yucca Mountain Site Characterization Project Waste Package Plan | 1 |
| E 1.99: conf-910435--53 | Interim waste storage for the Integral Fast Reactor | 1 |
| E 1.99: conf-910435--54 | Lubrication theory analysis of the permeability of rough-walled fractures | 1 |
| E 1.99: conf-910435--55 | Advances in the study of far-field phenomena affecting repository performance | 1 |
| E 1.99: conf-910435--56 | High-capacity, high-strength trailer designs for the GA-4/GA-9 Casks | 1 |
| E 1.99:conf-910435-60 | Historical overview of domestic spent fuel shipments | 1 |
| E 1.99: conf-910435--66 | Effect of ionizing radiation on the waste package environment | 1 |
