An experimental comparison of reactor power controllers based on the standard and alternate formulations of the dynamic period equation
Conference
·
· IEEE Trans. Nucl. Sci.; (United States)
OSTI ID:7090038
An experimental comparison was made of reactor power controllers based on the standard and alternate formulations of the dynamic period equation. Both controllers use the 'Reactivity Constraint Approach' which is a general methodology for the digital control of power in nuclear reactors that can be described using point kinetics. The standard formulation is the basis of the MIT-CSDL Non-Linear Digital Controller, a technique that has been licensed by the U.S. Nuclear Regulatory Commission for general use on the 5 MWt MIT Research Reactor. The alternate controller is newly developed. A principal strength of both controllers is that they address the time-delayed nature of reactor dynamics. The experiments show that while the overall response of the alternate controller is slower than that of its standard counterpart, the two do have comparable 80% rise times. Also, it is noted that there are certain advantages to use of the alternate formulation. Specifically, the derivation of the alternate dynamic period equation does not require the making of any assumptions, each of the alternate equation's component terms can be accurately measured on-line in real time, and no approximations are required in the development of the associated reactivity constraints.
- Research Organization:
- Nuclear Reactor Lab., Massachusetts Institute of Technology, 138 Albany Street, Cambridge, MA 02139
- OSTI ID:
- 7090038
- Report Number(s):
- CONF-861007-
- Conference Information:
- Journal Name: IEEE Trans. Nucl. Sci.; (United States) Journal Volume: NS-34:1
- 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
COMPARATIVE EVALUATIONS
COMPUTERS
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DIGITAL COMPUTERS
ENRICHED URANIUM REACTORS
EQUATIONS
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HEAVY WATER MODERATED REACTORS
KINETICS
MITR REACTOR
ON-LINE MEASUREMENT SYSTEMS
ON-LINE SYSTEMS
POWER RANGE 1-10 MW
REACTIVITY
REACTOR CONTROL SYSTEMS
REACTOR KINETICS
REACTORS
REAL TIME SYSTEMS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
TANK TYPE REACTORS
THERMAL REACTORS
TIME DEPENDENCE
TRAINING REACTORS
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
COMPARATIVE EVALUATIONS
COMPUTERS
CONTROL SYSTEMS
DIGITAL COMPUTERS
ENRICHED URANIUM REACTORS
EQUATIONS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
KINETICS
MITR REACTOR
ON-LINE MEASUREMENT SYSTEMS
ON-LINE SYSTEMS
POWER RANGE 1-10 MW
REACTIVITY
REACTOR CONTROL SYSTEMS
REACTOR KINETICS
REACTORS
REAL TIME SYSTEMS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
TANK TYPE REACTORS
THERMAL REACTORS
TIME DEPENDENCE
TRAINING REACTORS