Multimethods approach to safety-parameter-display evaluation

Conference · Fri Jan 01 04:00:00 EST 1982

OSTI ID:6807570

Banks, W W; Blackman, H S; Gertman, D I; Petersen, R J

The Human Factors Engineering Office of EG and G Idaho performed this NRC-funded study to assist the NRC in objectively assessing licensee-developed safety parameter display (SPD) formats and designs. The purpose of this study was to quantitatively measure the degree to which a tachistoscopic method of display evaluation would correlate with the results of a multidimensional rating approach to display evaluation. Results of the following three experiments will be presented; (a) tachistoscopic, (b) multidimensional rating scale, and (c) the combined results of a and b. The test material for all experiments consisted of three multivariate data display formats all under development as SPDs for reactor control rooms presenting safety parameter display data at the loss-of-fluid test (LOFT) facility. The three display formats studied were stars, deviation bar graphs, and meters. Eighteen adult volunteers were used as subjects. All were currently qualified reactor operators from the LOFT reactor plant, with a mean of 9.4 years reactor operating experience.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6807570
• Report Number(s): EGG-M-20382; CONF-821037-61; ON: DE83005016
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
CONSOLES
CONTROL ROOMS
CONTROL SYSTEMS
DISPLAY DEVICES
ENGINEERED SAFETY SYSTEMS
ENGINEERING
HUMAN FACTORS ENGINEERING
LOFT REACTOR
PERSONNEL
POWER REACTORS
PWR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTOR OPERATORS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS