Current applications of optimal estimation and control theory to the LOFT reactor plant
Conference
·
OSTI ID:6885344
Two advanced estimation and control systems being developed for the LOFT reactor plant are described and evaluated. The advanced protection system, based on a Kalman filter estimator is capable of providing on-line estimates of such critical variables as fuel and cladding temperature, DNBR, and LHGR. The steam generator LQG control system provides stable, closed-loop, zero steady state error control over a wide power range and also provides on-line estimates of certain unmeasureable variables as steam generator power output and cooling capacity for operator information.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6885344
- Report Number(s):
- CONF-801204-1; TRN: 80-018640
- Resource Relation:
- Conference: 19. IEEE conference, Albuquerque, NM, USA, 10 Dec 1980
- Country of Publication:
- United States
- Language:
- English
Similar Records
Advanced digital PWR plant protection system based on optimal estimation theory
Low-order model of the Loss-of-Fluid Test (LOFT) reactor plant for use in Kalman filter-based optimal estimators
Sensor placement algorithm development to maximize the efficiency of acid gas removal unit for integrated gasifiction combined sycle (IGCC) power plant with CO2 capture
Technical Report
·
Wed Apr 01 00:00:00 EST 1981
·
OSTI ID:6885344
Low-order model of the Loss-of-Fluid Test (LOFT) reactor plant for use in Kalman filter-based optimal estimators
Technical Report
·
Tue Jan 01 00:00:00 EST 1980
·
OSTI ID:6885344
Sensor placement algorithm development to maximize the efficiency of acid gas removal unit for integrated gasifiction combined sycle (IGCC) power plant with CO2 capture
Conference
·
Sun Jan 01 00:00:00 EST 2012
·
OSTI ID:6885344
+1 more
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOFT REACTOR
REACTOR CONTROL SYSTEMS
REACTOR PROTECTION SYSTEMS
MATHEMATICAL MODELS
CONTROL SYSTEMS
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220400* - Nuclear Reactor Technology- Control Systems
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOFT REACTOR
REACTOR CONTROL SYSTEMS
REACTOR PROTECTION SYSTEMS
MATHEMATICAL MODELS
CONTROL SYSTEMS
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220400* - Nuclear Reactor Technology- Control Systems
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors