Safety research programs sponsored by Office of Nuclear Regulatory Research: Quarterly progress report, April 1-June 30, 1986

Technical Report · Sat Nov 01 04:00:00 EST 1986

OSTI ID:6330694

Bari, R A; Bezler, P; Boccio, J L; Ginsberg, T; Greene, G A; Guppy, J G; Hall, R E; Hofmayer, C H; Khatib-Rahbar, H; Luckes, Jr, W J

This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Accident Evaluation, Division of Engineering Technology, and Division of Risk Analysis and Operations of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. The projects reported are the following: High Temperature Reactor Research, SSC Code Improvements, Thermal-Hydraulic Reactor Safety Experiments, Thermodynamic Core-Concrete Interaction Experiments and Analysis, Plant Analyzer, Code Assessment and Application, Code Maintenance (RAMONA-3B), MELCOR Verification and Benchmarking, Source Term Code Package Verification and Benchmarking, Uncertainty Analysis of the Source Term; Stress Corrosion Cracking of PWR Steam Generator Tubing, Soil-Structure Interaction Evaluation and Structural Benchmarks, Identification of Age Related Failure Modes; Application of HRA/PRA Results to Support Resolution of Generic Safety Issues Involving Human Performance, Protective Action Decisionmaking, Rebaseling of Risk for Zion, Containment Performance Design Objective, and Operational Safety Reliability Research.

• Research Organization: Brookhaven National Lab., Upton, NY (USA); Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6330694
• Report Number(s): NUREG/CR-2331-Vol.6-No.2; BNL-NUREG-51454-Vol.6-No.2; ON: TI87005050
• Country of Publication: United States
• Language: English

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