Call Number (LC) Title Results
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
E 1.99:EW7070601 Safety analysis report for packaging upgrade plan 1
E 1.99:EW7070602 Safety evaluation for packaging for the transport of K Basin sludge samples in the PAS-1 cask 1
E 1.99:EW7070902 Pollution prevention opportunity assessments, a training and resource guide
Return on investment (ROI) proposal preparation guide 		2
E 1.99: ex02mm120 Evaluation of the use of homogenized fuel assemblies in the thermal analysis of spent fuel storage casks
Radiant heat transfer from storage casks to the environment 		2
E 1.99: ex04c4020 RADIOLOGICAL EMISSIONS AND ENVIRONMENTAL MONITORING FOR BROOKHAV EN NATIONAL LABORATORY, 1947 - 1961. 1