Simulator evaluation of the Boiling Water Reactor Owners' Group (BWROG) graphics display system (GDS)
Technical Report
·
OSTI ID:6061267
This report describes the evaluation of a Graphic Display System (GDS). The GDS was developed by the Boiling Water Reactor Owners' Group (BWROG) to aid control room operators in detecting abnormal operating conditions, assessing the safety status of the plant, executing corrective action and monitoring plant response. The objective of the evaluation was to obtain recommendations for improving the usefulness of the GDS and to assess its usefulness under simulated accident operating conditions. The GDS presented 19 operator selectable displays on a high resolution color CRT monitor. The displays included safety function status, key parameters in bar and trend formats, and two-dimensional limits plots associated with the execution of symptom-based emergency procedures. Almost all of the operators, 94%, considered the GDS to be a useful device. The GDS was considered to be more useful for complex transients than for more straightforward events or routine operation.
- Research Organization:
- General Electric Co., San Jose, CA (USA); HPT, Inc., Thousand Oaks, CA (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6061267
- Report Number(s):
- ALO-1019; ON: DE83015160
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of a BWR graphics-display system
Development and evaluation of a graphic display system for BWRS
Graphic Display Development Program. Volume I, Revision 0
Technical Report
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:5236766
Development and evaluation of a graphic display system for BWRS
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:5236767
Graphic Display Development Program. Volume I, Revision 0
Technical Report
·
Fri Nov 30 23:00:00 EST 1984
·
OSTI ID:5761081
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
BWR TYPE REACTORS
CONSOLES
CONTROL ROOMS
CONTROL SYSTEMS
DISPLAY DEVICES
ENGINEERING
HUMAN FACTORS ENGINEERING
PERFORMANCE TESTING
PERSONNEL
REACTOR CONTROL SYSTEMS
REACTOR OPERATORS
REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
BWR TYPE REACTORS
CONSOLES
CONTROL ROOMS
CONTROL SYSTEMS
DISPLAY DEVICES
ENGINEERING
HUMAN FACTORS ENGINEERING
PERFORMANCE TESTING
PERSONNEL
REACTOR CONTROL SYSTEMS
REACTOR OPERATORS
REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS