Real time CRT displays for augmented operator capability at the Loss of Fluid Test nuclear reactor facility
Conference
·
OSTI ID:5339681
This paper describes the Loss-of-Fluid Test (LOFT) reactor data acquisition and graphic display system used at the Idaho National Engineering Laboratory (INEL). Specifically, the paper addresses the data presentation function of the system with particular emphasis on software considerations. The purpose of this discussion is to show how the LOFT facility utilizes the data acquisition and display system, in the interest of man/machine interface, within a critical environment involving the transfer and selection of large quantities of data.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5339681
- Report Number(s):
- EGG-M-11182; CONF-820689-3; ON: DE82018839
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
CONSOLES
CONTROL ROOMS
DATA ACQUISITION SYSTEMS
DISPLAY DEVICES
LOFT REACTOR
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
SPECIFICATIONS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
CONSOLES
CONTROL ROOMS
DATA ACQUISITION SYSTEMS
DISPLAY DEVICES
LOFT REACTOR
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
SPECIFICATIONS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS