Workshop on data-acquisition and -display systems: directions after TMI. [PWR; BWR]

Technical Report · Sat Nov 01 00:00:00 EST 1980

DOI:https://doi.org/10.2172/5746307· OSTI ID:5746307

The accident at Three Mile Island Unit-2 raised questions as to the adequacy of data acquisition and display systems in commercial nuclear power plants. A series of recommendations have developed from the various groups that have analyzed the accident in order to improve the oprator's overview of the plant safety conditions and to facilitate information transfer to technical support centers in emergency situations. This report is the result of an NSAC-sponsored workshop, where the various recommendations and emerging regulatory requirements were reviewed in an attempt to provide an integrated basis for their implementation.

• Research Organization: Technology for Energy Corp., Knoxville, TN (USA)
• OSTI ID: 5746307
• Report Number(s): EPRI-NSAC-6; ON: DE82901378; TRN: 82-006570
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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REACTOR INSTRUMENTATION
REACTOR PROTECTION SYSTEMS
DATA ACQUISITION SYSTEMS
DISPLAY DEVICES
PWR TYPE REACTORS
PERFORMANCE
SPECIFICATIONS
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WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
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