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List of results

• ML20050A697  + (A Study of Trench Covers to Minimize Infiltration at Waste Disposal Sites.Task 1 Report - Review of Present Practices and Annotated Bibliography)
• ML20214R316  + (A Study of Typical Nuclear Containment Purge Valves in an Accident Environment)
• ML20032C116  + (A Study of the Cavitation Process in a TWO-DIMENSIONAL Nozzle Using Pulsed Ruby Holography)
• ML20205N771  + (A Study of the Dispersed Flow Interfacial Heat Transfer Model of RELAP5/MOD2.5 and RELAP5/MOD3)
• ML20236D064  + (A Study of the Effects of Penetration Framing on Steel Containment Buckling Capacity)
• ML20053E756  + (A Study of the Feasibility of Microwave Dielectric Heating for LMFBR Transition Phase Accident Sequence Boiling Studies)
• ML20032C388  + (A Study of the Fixed Site Neutralization Model (Fsnm))
• ML19350E513  + (A Study of the Implications of Applying Quantitative Risk Criteria in the Licensing of Nuclear Power Plants in the United States)
• ML20137C168  + (A Study of the Operation and Maintenance of Computer Systems to Meet the Requirements of 10 CFR 73.55)
• ML18283B709  + (A Study of the Protection of Fish Larvae at Water Intakes Using Wedge-Wire Screening)
• ML20086N314  + (A Study of the Regulatory Position on Postulated Pipe Rupture Location Criteria)
• ML20247D793  + (A Study of the Use of Crosslinked HIGH-DENSITY Polyethylene for LOW-LEVEL Radioactive Waste Containers)
• ML20214A490  + (A Study on Ductile and Brittle Failure Design Criteria for Ductile CAST Iron SPENT-FUEL Shipping Containers)
• ML20154A355  + (A Study on Fabrication Criteria for Ductile CAST Iron SPENT-FUEL Shipping Containers)
• ML23332A157  + (A Study on the Characteristics of the Radiation Source Terms of Spent Fuel and Various Non-Fuel Hardware for Shielding Applications, Revision 1)
• ML19340E802  + (A Study to Determine the Feasibility of Conducting Epidemiologic Investigations of the Health Effects of LOW Level Ionizing Radiation.Phase 1 Report)
• ML19093A987  + (A Submission of a Proposed Design Change Which Allows the Lhsi Discharge Valves to Be Remotely Throttled from Control Room. Provides Completed Description of Tests Along with Evaluation of Results)
• ML20087M919  + (A Summary of Codes for Waste Package Performance Assessment)
• ML20072L599  + (A Summary of Computer Codes for Radiological Assessment)
• ML20207C257  + (A Summary of Environmentally Assisted CRACK-GROWTH Studies Performed at Westinghouse Electric Corporation.Under Funding from the Heavy-Section Steel Technology Program)
• ML20245L695  + (A Summary of HYDROGEN-AIR Detonation Experiments)
• ML20005E755  + (A Summary of Nuclear Power Plant Fire Safety Research at Sandia National LABORATORIES,1975-1987)
• ML20091R567  + (A Summary of ORNL Fission Product Release Tests with Recommended Release Rates and Diffusion Coefficients)
• ML20032D471  + (A Summary of Recent Investigations of Compact Specimen Geometry Effects on the JI-R Curve of HIGH-STRENGTH Steels)
• ML20081D109  + (A Summary of Repository Design Models)

• ML20062H255  + (A Summary of Repository Siting Models)

• ML20094P401  + (A Summary of the Fire Testing Program at the German HDR Test Facility)
• ML20072R488  + (A Summary of the Plant Electrical Systems (Pes) Study)
• ML20010H009  + (A Survey by Senior NRC Management to Obtain Viewpoints on the Safety Impact of Regulatory Activities from Representative Utilities Operating and Constructing Nuclear Power Plants)
• ML20032A472  + (A Survey by Senior NRC Management to Obtain Viewpoints on the Safety Impact of Regulatory Activities from Representative Utilities Operating and Constructing Nuclear Power Plants)
• ML20040F200  + (A Survey of Experimentally Determined Damping Values in Nuclear Power Plant Piping Systems)
• ML20052F624  + (A Survey of Methods for Improving Operator Acceptance of Computerized Aids)
• ML19341A903  + (A Survey of Potential Light Water Reactor Fuel Rod Failure Mechanisms and Damage Limits)
• ML20054A563  + (A Survey of Proposed Functional Requirements for a Disturbance Analysis and Surveillance System)
• ML20030D610  + (A Survey of Radioactive Effluent Releases from Byproduct Material Facilities)
• ML20248H701  + (A Survey of Repair Practices for Nuclear Power Plant Containment Metallic Pressure Boundaries)
• ML20072E792  + (A Survey of STATE-OF-THE-ART in Aging of Electronics with Application to Nuclear Power Plant Instrumentation)
• ML20005B306  + (A Survey of Safety Levels in Federal Regulation)
• ML20111B537  + (A Survey of the Uses of Radioactive Materials in Louisianas Offshore Waters)
• ML20246P925  + (A System for Generating Long Streamflow Records for Study of Floods of Long Return Period.Phase II)
• ML20141N957  + (A System for Generating Long Streamflow Records for Study of Floods of Long Return Period)
• ML20070G054  + (A Systematic Approach to Repetitive Failures)
• ML20073D876  + (A Systematic Process for Developing and Assessing Accident Management Plans)
• ML23122A126  + (A Systemic Perspective on NDE Strategies for Am Applications in Nuclear - Woy)
• ML20063N430  + (A TRAC-PD2 Analysis of a LARGE-BREAK LOSS-OF-COOLANT Accident in a Typical Us PWR)
• ML20236T988  + (A TRAC-PF1/MOD1 Analysis of the Ginna TUBE-RUPTURE Event on January 25,1982)
• ML24292A071  + (A Tail-Oriented Multi-Normal Model for Partially Correlated Seismic-Induced Failure Probabilities)
• ML20204J454  + (A Technical Basis for Revision to Anchorage Criteria)
• 05000354/FIN-2013002-01  + (A Technical Specification Surveillance Procedure for Remote Shutdown Panel Instrumentation was Inadequately Implemented)
• ML20027C451  + (A Technical Test Description of the NRC LONG-TERM Whole Rod and Crud Performance Test)
• ML20115A925  + (A Technique for Human Error Analysis (Atheana).Technical Basis and Methodology Description)