Experimental development of power reactor advanced controllers

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:5348458

Edwards, R M ^[1]; Weng, C K ^[2]; Lindsay, R W ^[3]

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1. Pennsylvania State Univ., University Park, PA (United States). Dept. of Nuclear Engineering
2. Pennsylvania State Univ., University Park, PA (United States). Dept. of Mechanical Engineering
3. Argonne National Lab., Idaho Falls, ID (United States)

A systematic approach for developing and verifying advanced controllers with potential application to commercial nuclear power plants is suggested. The central idea is to experimentally demonstrate an advanced control concept first on an ultra safe research reactor followed by demonstration on a passively safe experimental power reactor and then finally adopt the technique for improving safety, performance, reliability and operability at commercial facilities. Prior to completing an experimental sequence, the benefits and utility of candidate advanced controllers should be established through theoretical development and simulation testing. The applicability of a robust optimal observer-based state feedback controller design process for improving reactor temperature response for a TRIGA research reactor, Liquid Metal-cooled Reactor (LMR), and a commercial Pressurized Water Reactor (PWR) is presented to illustrate the potential of the proposed experimental development concept.

• Research Organization: Argonne National Lab., Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5348458
• Report Number(s): ANL/CP-75835; CONF-920538-26; ON: DE92014867
• Resource Relation: Conference: 8. power plant dynamics, control and testing symposium, Knoxville, TN (United States), 27-29 May 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
REACTOR CONTROL SYSTEMS
NUCLEAR POWER PLANTS
PWR TYPE REACTORS
RESEARCH REACTORS
CONTROL THEORY
DESIGN
FEEDBACK
TEMPERATURE MEASUREMENT
BREEDER REACTORS
CONTROL SYSTEMS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
NUCLEAR FACILITIES
POWER PLANTS
POWER REACTORS
REACTORS
RESEARCH AND TEST REACTORS
THERMAL POWER PLANTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220400* - Nuclear Reactor Technology- Control Systems
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210500 - Power Reactors
Breeding
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors