Digital control of power transients in a nuclear reactor
Conference
·
· IEEE Trans. Nucl. Sci.; (United States)
OSTI ID:6947964
An integrated, closed-loop, control system for on-line operations in nuclear power plants has been developed and demonstrated with an LSI-11/23 micro-processor on the 5 MWt fission reactor (MITR-II) that is operated by the Massachusetts Institute of Technology. This control system has inherent capabilities to perform on-line fault diagnosis, information display, sensor calibration, and measurement estimation. Recently, its scope has been extended to include the direct digital control of power changes ranging from 20-80% of the reactor's licensed limit. This controller differs from most of those discussed in theoretical and simulation studies by recognizing the non-linearity of reactor dynamics, calculating reactivity on-line, and controlling the rate of change of power by restricting both period and reactivity. The controller functions accurately using rods of non-linear worth in the presence of nonlinear feedback effects.
- Research Organization:
- Nuclear Reactor Laboratory Massachusetts Institute of Technology 138 Albany Street Cambridge, Massachusetts 02139
- OSTI ID:
- 6947964
- Report Number(s):
- CONF-831015-
- Conference Information:
- Journal Name: IEEE Trans. Nucl. Sci.; (United States) Journal Volume: 31:1
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
CALIBRATION
CLOSED-LOOP CONTROL
COMPUTER CALCULATIONS
COMPUTERIZED CONTROL SYSTEMS
CONTROL
CONTROL ELEMENTS
CONTROL ROD WORTHS
CONTROL SYSTEMS
DESIGN
DIGITAL SYSTEMS
ENRICHED URANIUM REACTORS
FAULT TREE ANALYSIS
FEEDBACK
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
MEASURING INSTRUMENTS
MITR REACTOR
MONITORS
NONLINEAR PROBLEMS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
ON-LINE CONTROL SYSTEMS
ON-LINE SYSTEMS
POWER PLANTS
RADIATION MONITORS
REACTIVITY
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TANK TYPE REACTORS
THERMAL POWER PLANTS
THERMAL REACTORS
TRAINING REACTORS
TRANSIENTS
220400* -- Nuclear Reactor Technology-- Control Systems
CALIBRATION
CLOSED-LOOP CONTROL
COMPUTER CALCULATIONS
COMPUTERIZED CONTROL SYSTEMS
CONTROL
CONTROL ELEMENTS
CONTROL ROD WORTHS
CONTROL SYSTEMS
DESIGN
DIGITAL SYSTEMS
ENRICHED URANIUM REACTORS
FAULT TREE ANALYSIS
FEEDBACK
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
MEASURING INSTRUMENTS
MITR REACTOR
MONITORS
NONLINEAR PROBLEMS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
ON-LINE CONTROL SYSTEMS
ON-LINE SYSTEMS
POWER PLANTS
RADIATION MONITORS
REACTIVITY
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TANK TYPE REACTORS
THERMAL POWER PLANTS
THERMAL REACTORS
TRAINING REACTORS
TRANSIENTS