| Call Number (LC) | Title | Results |
|---|---|---|
| E 1.99: ew4040000 | Thermal cleanups using dynamic underground stripping and hydrous pyrolysis oxidation | 1 |
| E 1.99: ew4040500 |
USE OF PERFLUOROCARBON TRACER (PFT) TECHNOLOGY FOR SUBSURFACE BARRIER INTEGRITY VERIFICATION AT THE WALDO TEST SITE Viscous liquid barrier demonstration at the Brookhaven National Laboratory Linac Isotope Producer |
2 |
| E 1.99:EW4040500 |
Leaching of radionuclides from furfural-based polymers used to solidify reactor compartments and components disposed of in the Arctic Kara Sea GAMMA IRRADIATION TESTING OF MONTAN WAX FOR USE IN WASTE MANAGEMENT SYSTEMS Furfural-based polymers for the sealing of reactor vessels dumped in the Arctic Kara Sea |
3 |
| E 1.99: ew4090100 |
Intraoral fiber optic-based diagnostic for periodontal disease Architectural Design Criteria for f-Block Metal Ion Sequestering Agents Final Report Mechanics of Bubbles in Sludges and Slurries The SX Solver A New Computer Program for Analyzing Solvent-Extraction Equilibria. Electrical properties of sand-clay mixtures the effect of microstructure. Laboratory Velocity Measurements Used for Recovering Soil Distributions from Field Seismic Data |
6 |
| E 1.99: ew4090200 | Relative Hazard Calculation Methodology | 1 |
| E 1.99:EW4090200 |
Verification of subsurface barrier integrity using perfluorocarbon gas tracers SAFETY ASPECTS RELATED TO THE RADIOACTIVELY CONTAMINATED FOREST AREAS IN BELARUS Decision support software technology demonstration plan |
3 |
| E 1.99: ew4510000 |
Influence of microstructural properties on geophysical measurements in sand-clay mixtures 3D finite-difference frequency-domain code for electromagnetic induction tomography |
2 |
| E 1.99:EW4510000 | The SX Solver A New Computer Program for Analyzing Solvent-Extraction Equilibria. | 1 |
| E 1.99: ew45100000 |
Ultrasonic characterization of synthetic soils for application to near surface geophysics Comparing geophysical measurements to theoretical estimates for soil mixtures at low pressures |
2 |
| E 1.99:EW7001000 |
Finance and supply management project execution plan Software configuration management plan for HANDI 2000 business management system Implementation plan for HANDI 2000 TWRS master equipment list |
3 |
| E 1.99: ew7002010 | Fire hazard analysis for Plutonium Finishing Plant complex | 1 |
| E 1.99:EW7002010 |
Plutonium reclamation facility (PRF), building 236-Z layup plan CSER 98-003 criticality safety evaluation report for PFP glovebox HC-21A with button can opening. CSER 99-002 CSER for unrestricted moderation of sludge material with two-boat operations in gloveboxes HC-21A and HC21-C. CSER 99-001 PFP LAB Dentirating calciner. An analysis of the impact of having uranium dioxide mixed in with plutonium dioxide |
5 |
| E 1.99:EW7003000 | CSER 98-003 Criticality safety evaluation report for PFP glovebox HC-21A with button can opening. | 1 |
| E 1.99:EW7030000 |
INERT Atmosphere confinement operability test procedure Thermal Stabilization FY 1999 blend plan |
2 |
| E 1.99: ew7040000 |
SNF fuel retrieval sub project safety analysis document Mechanical Analysis of an SM 2 Blk IV restrained firing within a concentric canister launcher test unit |
2 |
| E 1.99:EW7040000 |
Multi-Canister overpack sealing configuration MCO Monitoring issue closure package Multi-Canister overpack inservice inspection and maintenance System design description PFP thermal stabilization Sampling and analysis plan for the preoperational environmental survey of the spent nuclear fuel project facilities NAC-1 cask dose rate calculations for LWR spent fuel Estimates of particulate mass in multi-canister overpacks Supplementary information on K-Basin sludges Design package for fuel retrieval system fuel handling tool modification Thermal-hydraulic assessment of concrete storage cubicle with horizontal 3013 canisters Reaction rate constant for uranium in water and water vapor ASME Code requirements for multi-canister overpack design and fabrication Multi-Canister overpack number of shield plug ports Multi-Canister overpack design pressure rating Multi-Canister overpack dual pressure rating Multi-Canister overpack pressure testing MCO Monitoring activity description Multi-Canister overpack necessity of the rupture disk Multi-Canister overpack internal HEPA filters Design package Lazy Susan for the fuel retrieval system Sampling and analysis plan for sludge located on the floor and in the pits of the 105-K basins Maintenance and Operations study for K basins sludge treatment K Basin spent nuclear fuel characterization System design description for the consolidated sludge sampling system for K Basins floor and fuel canisters Revised sampling campaigns to provide sludge for treatment process testing Sampling and analysis plan for the consolidated sludge samples from the canisters and floor of the 105-K East basin Drying damaged K West fuel elements (Summary of whole element furnace runs 1 through 8) Data quality objectives for sampling of sludge from the K West and K East Basin floor and from other Basin areas MCO loading and cask loadout technical manual Test Plan for K Basin floor sludge consolidated sampling equipment Multi-Canister overpack ultrasonic examination of closure weld |
33 |
| E 1.99: ew7050000 | Documentation of remaining hazardous substances/dangerous waste in B Plant | 1 |
| E 1.99:EW7050000 | 324/327 facilities environmental effluent specifications | 1 |
| E 1.99:EW7070100 | Determining if a change to a proposal requires additional NEPA documentation the Smithsonian Solution. | 1 |
| E 1.99:EW7070200 | Hanford Site Environmental Surveillance Data 1997 | 1 |
