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

Technical Report · Sun Mar 01 04:00:00 EST 1987

OSTI ID:6541224

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; Luckas, Jr, W J

This progress report will describe 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: 6541224
• Report Number(s): NUREG/CR-2331-Vol.6-No.3; BNL-NUREG-51454-Vol.6-No.3; ON: TI87008840
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BATTERY CHARGERS
BOILERS
BOILING
CHEMICAL REACTIONS
COMPUTER CALCULATIONS
COMPUTERIZED SIMULATION
CONTAINMENT
CONTAINMENT SYSTEMS
CRACKING
DECOMPOSITION
ELECTRIC MOTORS
ELECTRICAL EQUIPMENT
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EQUIPMENT
FAILURES
FILM BOILING
FISSION PRODUCT RELEASE
FLUID FLOW
FLUID MECHANICS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HTGR TYPE REACTORS
HYDRAULICS
KINETICS
LIQUID METAL COOLED REACTORS
LOSS OF COOLANT
MECHANICS
MELTDOWN
MOTORS
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
PYROLYSIS
REACTOR ACCIDENTS
REACTOR KINETICS
REACTOR SAFETY
REACTORS
RELAYS
RESEARCH PROGRAMS
RISK ASSESSMENT
SAFETY
SEALS
SEISMIC EFFECTS
SIMULATION
SOIL-STRUCTURE INTERACTIONS
STEAM GENERATORS
THERMOCHEMICAL PROCESSES
TWO-PHASE FLOW
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS