Use of reactivity constraints for the automatic control of reactor power
Conference
·
· IEEE Trans. Nucl. Sci.; (United States)
OSTI ID:6135229
A theoretical framework for the automatic control of reactor power has been developed and experimentally evaluated on the 5 MWt Research Reactor that is operated by the Massachusetts Institute of Technology. The controller functions by restricting the net reactivity so that it is always possible to make the reactor period infinite at the desired termination point of a transient by reversing the direction of motion of whatever control mechanism is associated with the controller. This capability is formally designated as ''feasibility of control''. It has been shown experimentally that maintenance of feasibility of control is a sufficient condition for the automatic control of reactor power. This research should be of value in the design of closed-loop controllers, in the creation of reactivity displays, in the provision of guidance to operators regarding the timing of reactivity changes, and as an experimental envelope within which alternate control strategies can be evaluated.
- Research Organization:
- Massachusetts Inst. of Technology, Cambridge, MA
- OSTI ID:
- 6135229
- Report Number(s):
- CONF-841007-
- Conference Information:
- Journal Name: IEEE Trans. Nucl. Sci.; (United States) Journal Volume: NS-32:1
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
AUTOMATION
CONTROL
CONTROL SYSTEMS
ENRICHED URANIUM REACTORS
FEASIBILITY STUDIES
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
MITR REACTOR
REACTIVITY
REACTOR CONTROL SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
TANK TYPE REACTORS
THERMAL REACTORS
TRAINING REACTORS
TRANSIENTS
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
AUTOMATION
CONTROL
CONTROL SYSTEMS
ENRICHED URANIUM REACTORS
FEASIBILITY STUDIES
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
MITR REACTOR
REACTIVITY
REACTOR CONTROL SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
TANK TYPE REACTORS
THERMAL REACTORS
TRAINING REACTORS
TRANSIENTS