| Call Number (LC) | Title | Results |
|---|---|---|
| E 1.99:401001070C | ESTIMATING THE UNCERTAINTY IN REACTIVITY ACCIDENT NEUTRONIC CALCULATIONS | 1 |
| E 1.99:445698363 | Universal dynamic orchestration | 1 |
| E 1.99: 600301010 | Workshop on body composition in basic and clinical research and the emerging technologies | 1 |
| E 1.99: 600301020 |
JOINT STUDY OF IMPROVED SAFEGUARDS METHODOLOGY USING NO-NOTICE RANDOMIZED INSPECTION AT JNC'S Pu HANDLING FACILITIES AC losses in conductors based on high {Tc} superconductors |
2 |
| E 1.99: 820101000 |
Origin of the 871-keV gamma ray and the ̀̀oxide'' attribute Nuclear Energy Research Initiative. Development of a Stabilized Light Water Reactor Fuel Matrix for Extended Burnup Alternative TRUEX-Based Pretreatment Processing of INEEL Sodium Bearing Waste Relative Hazard and Risk Measure Calculation Methodology Rev1 Laboratory Studies of the Effects of Pressure and Dissolved Gas Supersaturation on Turbine-Passed Fish Assessment of Carbon Tetrachloride Groundwater Transport in Support of the Hanford Carbon Tetrachloride Innovative Technology Demonstration Program INSTALLATION OF A POST-ACCIDENT CONFINEMENT HIGH-LEVEL RADIATION MONITORING SYSTEM IN THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA |
7 |
| E 1.99:820101000 |
Property Data for Simulated Americium/Curium Glasses Characterization of Offgas Generated During Calcination of Incinerator Ash Surrogates Evaluation of Vitrification Processing Step for Rocky Flats Incinerator Ash |
3 |
| E 1.99: 820201000 |
Inorganic and Radiochemical Analysis of 241-C-104 Tank Waste Vitrification and Product Testing of AW-101 and AN-107 Pretreated Waste Particle Size (Sieving) and Enthalpy (Acid Calorimetry) Analysis of Single-Pull K East Basin Floor and Pit Sludges 100-D Area In Situ Redox Treatability Test for Chromate-Contaminated Groundwater Inorganic, Radioisotopic, and Organic Analysis of 241-AP-101 Tank Waste Qualification of Three On-Line Slurry Monitoring Devices for Application During Waste Retrieval Operations at DOE Sites Chemical and Radiochemical Analysis of Consolidated Sludge Samples from the K East Basin Test Plan for the Demonstration of Geophysical Techniques for Single-Shell Tank Leak Detection at the Hanford Mock Tank Site Fiscal Year 2001. Material Balance Assessment for Double-Shell Tank Waste Pipeline Transfer Second ILAW Site Borehole Characterization Plan Evaluation of the Magnesium Hydroxide Treatment Process for Stabilizing PFP Plutonium/Nitric Acid Solutions Results of Waste Transfer and Back-Dilution in Tanks 241-SY-101 and 241-SY-102 TCLP Preparation and Analysis of K East Basin Composite Sludge Samples Ammonia Results Review for Retained Gas Sampling Particle Size Distribution Data From Existing Boreholes at the Immobilized Low-Activity Waste Site Results of Tritium Tracking and Groundwater Monitoring at the Hanford Site 200 Area State-Approved Land Disposal Site Fiscal Year 2000 Review of Waste Retrieval Sluicing System Operations and Data for Tanks 241-C-106 and 241-AY-102 Review of Upscaling Methods for Describing Unsaturated Flow Thermal Decomposition of Radiation-Damaged Polystyrene Data quality objectives for moisture measurement in stabilized special nuclear material UNSAT-H Version 3.0 Unsaturated Soil Water and Heat Flow Model Theory, User Manual, and Examples. Overview of the Flammability of Gases Generated in Hanford Waste Tanks Groundwater Monitoring and Tritium-Tracking Plan for the 200 Area State-Approved Land Disposal Site Pump Jet Mixing and Pipeline Transfer Assessment for High-Activity Radioactive Wastes in Hanford Tank 241-AZ-102 User's Guide for MetView A Meteorological Display and Assessment Tool. Statistical evaluation of effluent monitoring data for the 200 Area Treated Effluent Disposal Facility Evaluation of the potential for agricultural development at the Hanford Site Expert Panel Recommendations for Hanford Double-Shell Tank Life Extension Gas Releases During Saltcake Dissolution for Retrieval of Single-Shell Tank Waste A Survey of Vapors in the Headspaces of Single-Shell Waste Tanks Testing and Analysis of Consolidated Sludge Samples from the 105 K East Basin Floor and Canisters Compilation and Integration of K Basin Sludge Particle Size Analysis Data Regulatory DQO Test Plan for Determining Method Detection Limits, Estimated Quantitation Limits, and Quality Assurance Criteria for Specified Analytes Statistical Evaluation of Effluent Monitoring Data for the 200 Area Treated Effluent Disposal Facility Waste Form Release Calculations for the 2001 Immobilized Low-Activity Waste Performance Assessment Cold Vacuum Drying Facility Stack Air Sampling System Qualification Tests Gas Releases During Saltcake Dissolution for Retrieval of Single-Shell Tank Waste, Rev. 1 Test Plan for Field Experiments to Support the Immobilized Low-Activity Waste Disposal Performance Assessment at the Hanford Site Qualification Tests for the Air Sampling System at the 296-Z-7 Stack Results of Tritium Tracking and Groundwater Monitoring at the Hanford Site 200 Area State-Approved Land Disposal Site--Fiscal Year 2001 Geochemical Data Package for the Hanford Immobilized Low-Activity Tank Waste Performance Assessment (ILAWPA) Preventing Buoyant Displacement Gas Release Events in Hanford Double-Shell Waste Tanks Rheological Studies on Pretreated Feed and Melter Feed from AW-101 and AN-107 Rheological Studies on Pretreated Feed and Melter Feed from C-104 and AZ-102 Waste Tank Size Determination for the Hanford River Protection Project Cold Test, Training, and Mockup Facility Vitrification and Product Testing of C-104 and AZ-102 Pretreated Sludge Mixed with Flowsheet Quantities of Secondary Wastes Diffusion and Leaching of Selected Radionuclides (Iodine-129, Technetium-99, and Uranium) Through Category 3 Waste Encasement Concrete and Soil Fill Material Summary of Tritium Tracking and Groundwater Monitoring at the Hanford Site 200 Area SALDS - FY 1998 Recharge Data Package for the Immobilized Low-Activity Waste 2001 Performance Assessment |
52 |
| E 1.99:820201000 |
Buoyancy and Dissolution of the Floating Crust Layer in Tank 241-SY-101 During Transfer and Back-Dilution In Situ Void Fraction and Gas Volume in Hanford Tank 241-SY-101 as Measured with the Void Fraction Instrument K Basin Sludge Conditioning Process Testing Partitioning of PCBs in Dissolver Solution After Neutralization/Precipitation (Caustic Adjustment) K Basin Sludge Conditioning Process Testing Fate of PCBs During K Basin Sludge Dissolution in Nitric Acid and with Hydrogen Peroxide Addition Good Practice Guide Waste Minimization/Pollution Prevention Results of Tritium Tracking and Groundwater Monitoring at the Hanford Site 200 Area State-Approved Land Disposal Site-FY1999 Potential for Waste Stratification from Back-Dilution in Tank 241-SY-101 Effects of Crust Ingestion on Mixer Pump Performance in Tank 241-SY-101 Workshop Results. A Discussion of SY-101 Crust Gas Retention and Release Mechanisms Thermal and Radiolytic Gas Generation Tests on Material from Tanks 241-U-103, 241-AW-101, 241-S-106, and 241-S-102 Status Report. Buoyant Response of the Tank 241-SY-101 Crust to Transfer and Back-Dilution |
11 |
| E 1.99: 830403000 |
Evaluation of Elevated Tritium Levels in Groundwater Downgradient from the 618-11 Burial Ground Phase I Investigations A Catalog of Geologic Data for the Hanford Site Roadmap for Integrating Sustainable Design into Site-Level Operations A Catalog of Vadose Zone Hydraulic Properties for the Hanford Site Measurement of Helium-3/Helium-4 Ratios in Soil Gas at the 618-11 Burial Ground |
5 |
| E 1.99:960300000 | BROOKHAVEN NATIONAL LABORATORY SITE ENVIRONMENTAL REPORT FOR CALENDAR YEAR 1997. | 1 |
| E 1.99:963238725 | West Virginia Full-Scale Solar Energy Team Growing the Mountain State Energy Economy by Reaching our Full Solar Potential | 1 |
| E 1.99: a | RE-ENTRY AND DISPOSAL PHENOMENA FOR NUCLEAR AUXILIARY POWER SYSTEMS. THE SCALING OF PROCESSES OF SIGNIFICANCE IN THE RE-ENTRY OF NUCLEAR FUEL ELEMENTS | 1 |
| E 1.99:(a) | SODIUM-HEATED STEAM GENERATOR DEVELOPMENT. Addendum to PRELIMINARY DESIGN REPORT, FULL-SIZE GENERATOR | 1 |
| E 1.99: a-1 project |
USE OF FISSION PRODUCT GAS AS A GAMMA SOURCE Calculation of {tau} for delayed neutrons Data on indium sulfate HEATING AND COOLING OF THE INDIUM BLANKET, THERMAL SHIELD, AND SHIELDING POOL ANALYSIS OF THE EXTERNAL LOOP DECAY FOR A NUCLIDE PRODUCED IN A NUCLEAR REACTOR COOLING OF THE FOOD IRRADIATION REACTOR CORE NUCLEAR CONSIDERATIONS ON BLANKET PRODUCTION OF ISOTOPES USING A CORE OF MTR FUEL ELEMENTS PARAMETER STUDY OF A-1 REACTOR Gamma attenuation in externally irradiated cylindrical targets and gamma flux distributions within cylindrical sources Mev yield per neutron captured for elements of promise for a gamma reactor AN INVESTIGATION OF PRODUCTION RATE, DWELL TIME WITH COMMENTS ON DOSE Homogeneous reactor circulating fuel system as a gamma source Gamma attenuation in targets irradiated by slab sources Discussion of homogeneous reactor possibilities Decontamination and waste disposal in indium gamma irradiation facility Airborne hazards due to indium in radiation reactor PHOTONEUTRONS IN FOOD IRRADIATED BY Na$sup 2$$sup 4$ Concerning the direct use of core gammas for food irradiation NUCLEAR CONSIDERATIONS ON THE USE OF Na IN BeO AND GRAPHITE CORES AS A POTENTIAL GAMMA SOURCE ISOTOPE PRODUCTION IN A CORE OF MTR TYPE FUEL ELEMENTS |
20 |
| E 1.99: a-4.390.31 | CRITICAL DIMENSIONS OF UNTAMPED CONICAL VESSELS | 1 |
| E 1.99: a-6.410.8 | EFFECTS OF RECEIVER SLOTS ON QUANTITY AND QUALITY OF PRODUCT AND RECYCLE | 1 |
| E 1.99: a-6.465.1 | PROCESS MONITOR ANALYSIS VICTOREEN MODEL 350 | 1 |
| E 1.99: a-7.390.16 | METHOD OF DETERMINING SOLID ANGLES. (Applicable to Critical Mass Studies) | 1 |
| E 1.99: a-7.390.21 | CRITICALITY IN GRAPHITE SYSTEMS | 1 |
| E 1.99: a-7.390.22 | CRITICAL CONDITIONS IN CYLINDRICAL VESSELS | 1 |
