Twenty-third water reactor safety information meeting: Volume 2, Human factors research; Advanced I and C hardware and software; Severe accident research; Probabilistic risk assessment topics; Individual plant examination: Proceedings
- comp.; Brookhaven National Lab., Upton, NY (United States)
This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 2, present topics in human factors research, advanced instrumentation and control hardware and software, severe accident research, probabilistic risk assessment, and individual plant examination. Individual papers have been cataloged separately.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab. (BNL), Upton, NY (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 231340
- Report Number(s):
- NUREG/CP-0149-Vol.2; CONF-9510156-Vol.2; ON: TI96007985; TRN: 96:014233
- Resource Relation:
- Conference: 23. water reactor safety information meeting, Bethesda, MD (United States), 23-25 Oct 1995; Other Information: PBD: Mar 1996
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
REACTOR SAFETY
MEETINGS
BWR TYPE REACTORS
PWR TYPE REACTORS
NUCLEAR POWER PLANTS
LEADING ABSTRACT
HUMAN FACTORS
CONTROL ROOMS
REACTOR OPERATORS
MAN-MACHINE SYSTEMS
REMOTE SENSING
REACTOR INSTRUMENTATION
QUALITY ASSURANCE
FIBER OPTICS
COMPUTERIZED CONTROL SYSTEMS
REACTOR ACCIDENTS
FUEL-COOLANT INTERACTIONS
CORIUM
M CODES
STEAM GENERATORS
CRITICAL HEAT FLUX
EXPLOSIONS
HYDROGEN
COMBUSTION
S CODES
R CODES
COMPUTERIZED SIMULATION
RISK ASSESSMENT
DATA COVARIANCES
INSPECTION
CONTAINMENT