Call Number (LC) | Title | Results |
---|---|---|
E 1.99:101122004 | Executive Summary of the Workshop on Subcritical Neutron Production | 1 |
E 1.99:105016100 | Deduction and Analysis of the Interacting Stress Response Pathways of Metal/Radionuclide-reducing Bacteria | 1 |
E 1.99:0000000288503539 | Factors Determining the Interaction of CO2 and CH4 on Shale in Appalachian Basin | 1 |
E 1.99:357827039 | Versatile intangible projection | 1 |
E 1.99: 400403209 |
In situ redox manipulation of subsurface sediments from Fort Lewis, Washington Iron reduction and TCE dechlorination mechanisms. Monitoring and Evaluation of the Prototype Surface Collector at Bonneville First Powerhouse in 2000 Synthesis of Results. Evaluation of the Fish Passage Effectiveness of the Bonneville I Prototype Surface Collector using Three-Dimensional Ultrasonic Fish Tracking Water Velocity Measurement on an Extended-Length Submerged Bar Screen at John Day Dam Light-Emitting Tag Testing in Conjunction with Testing of the Minimum Gap Runner Turbine Design at Bonneville Dam Powerhouse 1 Decision Document for the Storm Water Outfalls/Industrial Wastewater Treatment Plant, Pesticide Rinse Area, Old Fire Fighting Training Pit, Illicit PCB Dump Site, and the Battery Acid Pit Fort Lewis, Washington Comparison of Intake Gate Closure Methods At Lower Granite, Little Goose, Lower Monumental, And McNary Dams Using Risk-Based Analysis In Situ Redox Manipulation of Subsurface Sediments from Fort Lewis, Washington Iron Reduction and TCE Dechlorination Mechanisms. Bonneville Second Powerhouse Tailrace and High Flow Outfall ADCP and drogue release field study. Observations of the Behavior and Distribution of Fish in Relation to the Columbia River Navigation Channel and Channel Maintenance Activities Simulation of Tailrace Hydrodynamics Using Computational Fluid Dynamics Models |
11 |
E 1.99:400403209 |
SURVEY OF NOISE SUPPRESSION SYSTEMS FOR ENGINE GENERATOR SETS. Federal Emergency Management Information System (FEMIS) Bill of Materials (BOM) for FEMIS Version 1.4.6 |
2 |
E 1.99: 400403309 | National Counterdrug Center (NCC) Simulation System Operational Requirements Document (ORD) Version 2 | 1 |
E 1.99: 400403809 | Chemical Emission Scenarios and Detection Limits for Active Infrared Remote Sensing | 1 |
E 1.99: 400408000 |
TREATABILITY STUDY ON THE USE OF BY-PRODUCT SULFUR IN KAZAKHSTAN FOR THE STABILIZATION OF HAZARDOUS AND RADIOACTIVE WASTES. OPENING COMMENTS TO THE SPECIAL SESSION ON DECISION SUPPORT TOOLS. Post-remediation biomonitoring of pesticides and other contaminants in marine waters and sediment near the United Heckathorn Superfund Site, Richmond, California LOW LEVEL LIQUID RADIOACTIVE WASTE TREATMENT AT MURMANSK, RUSSIA FACILITY UPGRADE AND EXPANSION. FRAMEWORK FOR DECISION SUPPORT USED IN CONTAMINATED LAND MANAGEMENT IN EUROPE AND NORTH AMERICA. REVIEW OF DISCUSSIONS ABOUT DECISION SUPPORT ISSUES IN EUROPE AND NORTH AMERICA AT THE NATO CCMS SPECIAL SESSION, AND OVERALL CONCLUSIONS. Year 4 Post-Remediation Biomonitoring of Pesticides and Other Contaminants in Marine Waters Near the United Heckathorn Superfund Site, Richmond, California USE OF PERFLUOROCARBON TRACER (PFT) TECHNOLOGY FOR SUBSURFACE BARRIER INTEGRITY VERIFICATION AT THE WALDO TEST SITE. |
9 |
E 1.99:400408000 |
THE MURMANSK INITIATIVE - RF COMPLETING CONSTRUCTION AND START-UP TESTING. Surface Water-Sediment Feasibility Study Report for the McCormick and Baxter Superfund Site, Stockton, California |
2 |
E 1.99: 400412000 |
ADENOVIRUS PROTEINASE-ANTIVIRAL TARGET FOR TRIPLE-COMBINATION THERAPY ON A SINGLE ENZYME POTENTIAL INHIBITOR-BINDING SITES. ADENOVIRUS INTERACTION WITH ITS CELLULAR RECEPTOR CAR. |
2 |
E 1.99: 400480000 |
Analysis of hazardous biological material by MALDI mass spectrometry Nucleic Acid-Based Detection and Identification of Bacterial and Fungal Plant Pathogens - Final Report CRACOW CLEAN FOSSIL FUELS AND ENERGY EFFICIENCY PROGRAM - FINAL REPORT |
3 |
E 1.99: 400801000 |
RESPONSE TO THE CHALLENGES OF TECHNOLOGICAL CHANGE ON A SAFEGUARDS EQUIPMENT SUPPORT ORGANIZATION DESIGN OF A PERFORMANCE-BASED TRAINING PROGRAM. U.S. SUPPORT PROGRAM CONTRIBUTIONS TO REMOTE MONITORING LESSONS LEARNED IN TESTING OF SAFEGUARDS EQUIPMENT. PLANNING FOR THE FUTURE OF THE U.S. SUPPORT PROGRAM. |
4 |
E 1.99:400801000 | RECRUITMENT OF U.S. CITIZENS FOR VACANCIES IN IAEA SAFEGUARDS | 1 |
E 1.99: 401001060 |
STRUCTURAL PERFORMANCE OF DEGRADED REINFORCED CONCRETE MEMBERS. IDENTIFICATION OF FREE-FIELD SOIL PROPERTIES USING NUPEC RECORDED GROUND MOTIONS. PREDICTION OF NUPECS MULTI-AXIS LOADING TESTS OF CONCRETE SHEAR WALLS. EFFECTS OF PARAMETRIC VARIATIONS ON SEISMIC ANALYSIS METHODS FOR NON-CLASSICALLY DAMPED COUPLED SYSTEMS HUMAN FACTORS GUIDANCE FOR CONTROL ROOM EVALUATION SURVEYS OF ORGANIZATIONAL CULTURE AND SAFETY CULTURE IN NUCLEAR POWER ASSESSMENT OF CABLE AGING USING CONDITION MONITORING TECHNIQUES AN EVALUATION OF CONDITION MONITORING TECHNIQUES FOR LOW-VOLTAGE ELECTRIC CABLES A QUALITATIVE APPROACH TO UNCERTAINTY ANALYSIS FOR THE PWR ROD EJECTION ACCIDENT STRUCTURAL RESPONSE OF DEGRADED REINFORCED CONCRETE COMPONENTS. AGE-RELATED DEGRADATION OF STRUCTURES AND PASSIVE COMPONENTS AT NUCLEAR POWER PLANTS. OVERVIEW ON THE NRC-BNL BENCHMARK EVALUATION PROGRAM OF SEISMIC ANALYSIS METHODS FOR NON-CLASSICALLY DAMPED COUPLED SYSTEMS. USING CONDITION MONITORING TO PREDICT REMAINING LIFE OF ELECTRIC CABLES. ASSESSMENT OF THE RELEVANCE OF DISPLACEMENT BASED DESIGN METHODS/CRITERIA TO NUCLEAR PLANT STRUCTURES. A BENCHMARK PROGRAM FOR EVALUATION OF METHODS FOR COMPUTING SEISMIC RESPONSE OF COUPLED BUILDING-PIPING/EQUIPMENT WITH NON-CLASSICAL DAMPING. COMPUTERIZATION OF NUCLEAR POWER PLANT EMERGENCY OPERATING PROCE DURES. |
16 |
E 1.99:401001060 |
NRC-BNL BENCHMARK PROGRAM ON EVALUATION OF METHODS FOR SEISMIC ANALYSIS OF COUPLED SYSTEMS. NRC SUPPORT FOR THE KALININ (VVER) PROBABILISTIC RISK ASSESSMENT INTERCOMPARISON OF RESULTS FOR A PWR ROD EJECTION ACCIDENT AGE-RELATED DEGRADATION OF NUCLEAR POWER PLANT STRUCTURES AND COMPONENTS. DISPLACEMENT BASED SEISMIC DESIGN CRITERIA EVALUATION OF MODAL COMBINATION METHODS FOR SEISMIC RESPONSE SPECTRUM ANALYSIS. FIRE SAFETY IN NUCLEAR POWER PLANTS A RISK-INFORMED AND PERFORMANCE-BASED APPROACH. |
7 |
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 |