A comparison of fuzzy logic-PID control strategies for PWR pressurizer control

Conference · Fri Jan 01 00:00:00 EST 1993 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5882983

Kavaklioglu, K; Ikonomopoulos, A ^[1]

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1. Univ. of Tennessee, Knoxville (United States)

This paper describes the results obtained from a comparison performed between classical proportional-integral-derivative (PID) and fuzzy logic (FL) controlling the pressure in a pressurized water reactor (PWR). The two methodologies have been tested under various transient scenarios, and their performances are evaluated with respect to robustness and on-time response to external stimuli. One of the main concerns in the safe operation of PWR is the pressure control in the primary side of the system. In order to maintain the pressure in a PWR at the desired level, the pressurizer component equipped with sprayers, heaters, and safety relief valves is used. The control strategy in a Westinghouse PWR is implemented with a PID controller that initiates either the electric heaters or the sprayers, depending on the direction of the coolant pressure deviation from the setpoint.

• OSTI ID: 5882983
• Report Number(s): CONF-930601-; CODEN: TANSAO
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 68; Conference: American Nuclear Society (ANS) annual meeting, San Diego, CA (United States), 20-24 Jun 1993; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
PRESSURE CONTROL
REACTOR CONTROL SYSTEMS
FUZZY LOGIC
SAFETY
COMPARATIVE EVALUATIONS
COMPUTERIZED CONTROL SYSTEMS
TIME DEPENDENCE
TRANSIENTS
CONTROL
CONTROL SYSTEMS
ENRICHED URANIUM REACTORS
EVALUATION
MATHEMATICAL LOGIC
ON-LINE CONTROL SYSTEMS
ON-LINE SYSTEMS
POWER REACTORS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220400* - Nuclear Reactor Technology- Control Systems
220900 - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled