Call Number (LC) Title Results
E 1.99: ew40 Uranium Mobility During In Situ Redox Manipulation of the 100 Areas of the Hanford Site 1
E 1.99:EW40 100-D Area In Situ Redox Treatability Test for Chromate-Contaminated Groundwater FY 1998 Year-End Report. 1
E 1.99:EW4010 A Modular Computer Code for Simulating Reactive Multi-Species Transport in 3-Dimensional Groundwater Systems
Development of Alkaline Oxidative Dissolution Methods for Chromium (III) Compounds Present in Hanford Site Tank Sludges
Selection of AT-Tank Analysis Equipment for Determining Completion of Mixing and Particle Concentration in Hanford Waste Tanks 		3
E 1.99: ew401000 Glass Formulation for Idaho National Engineering and Environmental Laboratory Zirconia Calcine High-Activity Waste 1
E 1.99: ew4010000 Pilot-Scale Test of Counter-Current Ion Exchange (CCIX) Using UOP IONSIV IE-911
Hanford immobilized LAW product acceptance Initial Tanks Focus Area testing data package.
Status Report on Phase Identification in Hanford Tank Sludges
Comparability of ISOCS instrument in radionuclide characterization at Brookhaven National Laboratory
EFFECT OF RADIATION ON SPINEL CERAMICS FOR PERMANENT CONTAINERS FOR NUCLEAR WASTE TRANSPORTATION AND STORAGE.
CHARACTERIZATION OF LEAK PATHWAYS IN THE BELOW GRADE DUCTS OF THE BROOKHAVEN GRAPHITE RESEARCH REACTOR USING PERFLUOROCARBON TRACERS.
Test Summary Report INEEL Sodium-Bearing Waste Vitrification Demonstration RSM-01-1
Database and Interim Glass Property Models for Hanford HLW Glasses
Letter Report. Defense Waste Processing Facility Pour Spout Heaters - Conceptual Designs and Modeling
Evaluation of SAFT/T-SAFT Technology for the Inspection of Hanford's Double Shell Waste Tank Knuckle Regions
Comparison of Nozzles and Flow Straighteners for Tank Waste Sluicing Applications
USING PERFLUOROCARBON TRACERS FOR VERIFICATION OF CAP AND COVER SYSTEMS PERFORMANCE.
Noble Metals and Spinel Settling in High Level Waste Glass Melters
Subsurface Contaminant Focus Area Monitored Natural Attenuation (MNA)--Programmatic, Technical, and Regulatory Issues.
DEPLOYMENT OF INNOVATIVE CHARACTERIZATION TECHNOLOGIES AND IMPLEMENTATION OF THE MARSSIM PROCESS AT RADIOLOGICALLY CONTAMINATED SITES.
Sulfur Partitioning During Vitrification of INEEL Sodium Bearing Waste Status Report.
High-Level Waste Melter Study Report
Radionuclide Activities in Contaminated Soils Effects of Sampling Bias on Remediation of Coarse-Grained Soils in Hanford Formation.
Enhanced Site Characterization of the 618-4 Burial Ground
Identification of a Hanford Waste Site for Initial Deployment of the In Situ Gaseous Reduction Approach
Formulation Efforts for Direct Vitrification of INEEL Blend Calcine Waste Simulate Fiscal Year 2000.
Tanks Focus Area Site Needs Assessment - FY 2001
Functions and Requirements for the DST Knuckle Region Ultrasonic Scanning System
ACCELERATED SITE TECHNOLOGY DEPLOYMENT COST AND PERFORMANCE REPORT COMPARABILITY OF ISOCS INSTRUMENT IN RADIONUCLIDE CHARACTERICATION AT BROOKHAVEN NATIONAL LABORATORY
DISTRIBUTED CONTAINER FAILURE MODELS FOR THE DUST-MS COMPUTER CODE.
Preliminary Feasibility Study of Using Solid-State Nuclear Magnetic Resonance Spectroscopy to Characterize Hanford Tank Waste Solids
Caustic Leaching of Hanford Tank S-110 Sludge
Technical Review of Retrieval and Closure Plans for the INEEL INTEC Tank Farm Facility
Description of Work for Drilling at the 183-DR Site in Support of the In Situ Gaseous Reduction Test
DEVELOPMENT AND DEMONSTRATION OF POLYMER MICROENCAPSULATION OF MIXED WASTE USING KINETIC MIXER PROCESSING
FEASIBILITY STUDY OF DUPOLY TO RECYCLE DEPLETED URANIUM.
Oak Ridge National Laboratory Old Hydrofracture Facility Waste Remediation Using the Borehole-Miner Extendible-Nozzle Sluicer
Semivolatile organic (GC-MS) and inorganic analyses of groundwater samples during the hydrous pyrolysis/oxidation (HPO) field test in Visalia, CA, 1997
An integrated approach to monitoring a field test of in situ contaminant destruction 		36
E 1.99:EW4010000 Tank 241-AZ-101 prototype corrosion probe two-year status report
LOW TEMPERATURE GLASSES FOR HANFORD TANK WASTES.
USE OF RECYCLED POLYMERS FOR ENCAPSULATION OF RADIOACTIVE, HAZARDOUS AND MIXED WASTES
TREATABILITY STUDY FOR POLYETHYLENE MICROENCAPSULATION OF COMMERCIALLY GENERATED DSSI ASH MIXED WASTE.
THERMOPLASTIC ENCAPSULATION TREATABILITY STUDY OF FERNALD SILO 1 AND SILO 3 WASTES.
MERCURY BAKEOFF TECHNOLOGY COMPARISON FOR THE TREATMENT OF MIXED WASTE MERCURY CONTAMINATED SOILS AT BNL.
Corrosion data from Hanford High-Level waste tank 241-AN-107
Analysis of the effects of corrosion probe on riser 241-AN-102-WST-16 during seismic event
Glass Formulation Development for INEEL Sodium-Bearing Waste
TFA Tanks Focus Area Multiyear Program Plan FY00-FY04
Design of multi-function Hanford tank corrosion monitoring system 		15
E 1.99:EW4020 RENDERING ASBESTOS HARMLESS. TRANSCRIPT OF 339TH BROOKHAVEN LECTURE. OCTOBER 21, 1998 1
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
Mechanics of Bubbles in Sludges and Slurries
Architectural Design Criteria for f-Block Metal Ion Sequestering Agents Final Report
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 SAFETY ASPECTS RELATED TO THE RADIOACTIVELY CONTAMINATED FOREST AREAS IN BELARUS
Verification of subsurface barrier integrity using perfluorocarbon gas tracers
Decision support software technology demonstration plan 		3
E 1.99: ew4510000 3D finite-difference frequency-domain code for electromagnetic induction tomography
Influence of microstructural properties on geophysical measurements in sand-clay mixtures 		2
E 1.99:EW4510000 The SX Solver A New Computer Program for Analyzing Solvent-Extraction Equilibria. 1
E 1.99: ew45100000 Comparing geophysical measurements to theoretical estimates for soil mixtures at low pressures
Ultrasonic characterization of synthetic soils for application to near surface geophysics 		2
E 1.99:EW7001000 Software configuration management plan for HANDI 2000 business management system
Finance and supply management project execution plan
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 CSER 99-001 PFP LAB Dentirating calciner.
Plutonium reclamation facility (PRF), building 236-Z layup plan
An analysis of the impact of having uranium dioxide mixed in with plutonium dioxide
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. 		5
E 1.99:EW7003000 CSER 98-003 Criticality safety evaluation report for PFP glovebox HC-21A with button can opening. 1