Multivariable feedback control applications in combustion engineering high power density pressurized water reactors
Creators
- 1. Combustion Engineering, Inc., Windsor, CT (USA). Nuclear Power Systems
- 2. Ente Nazionale per l'Energia Elettrica, Milan (Italy). Centro di Ricerca Automatica
Description
The Multivariable Frequency Response technique was used to design a control system for Pressurized Water Reactors. The technique is based on a generalization of the frequency response approach to control system design. The aim of the study was to evaluate the feasibility of automatic control of Pressurized Water Reactors of Combustion Engineering design. The objectives for the design of the control system were to maintain core parameters within their design limits, eliminate boron over- and undershoots during load changes, emphasize axial shape control when approaching rated power, reduce control rod motion and permit deviations from the primary coolant temperature program where practical. The performance of the simulated control system was evaluated using a model of a Nuclear Steam Supply System with a 3-dimensional nodal reactor core representation. An analysis of PWR load changes showed that the power distribution and the average reactor coolant temperature can be adequately controlled automatically. The performance of the simulated control system for a variety of core conditions, demonstrated the potential usefulness of automatic multivariable feedback control in Pressurized Water Reactors. (orig.)
Abstract (German)
Fuer die Auslegung eines DWR-Regelsystems wurde die 'Multivariable Frequency Response'-Technik benutzt. Die Technik beruht auf einer Verallgemeinerung des Frequenz-Antwort-Verfahrens zur Auslegung von Regelsystemen. Ziel der Untersuchung war es, die Durchfuehrbarkeit der automatischer Regelung fuer DWR von Combustion Engineering zu zeigen. Auslegungskriterien fuer das Regelsystem waren, die Auslegungsgrenzen fuer die Kernparameter einzuhalten, eine Borueber- und -unterspeisung waehrend Lastwechseln auszuschliessen, die Regelung der axialen Leistungsverteilung bei Annaeherung an die Nennleistung zu verstaerken, die Regelstabbewegung einzuschraenken und Abweichungen von der vorprogrammierten Hauptkuehlmitteltemperatur zuzulassen, wenn dies praktisch erscheint. Das Verhalten des simulierten Regelsystems wurde mit Hilfe eines Modells eines nuklearen Dampferzeugungsystems mit dreidimensionaler Knotenpunktsdarstellung des Reaktorkerns untersucht. Eine Analyse von DWR-Lastwechseln zeigte, dass die Leistungsverteilung und die mittlere Hauptkuehlmitteltemperatur ausreichend automatisch geregelt werden koennen. Das Verhalten des simulierten Regelsystems bei einer Vielzahl von Kernzustaenden hat die potentielle Brauchbarkeit der automatischen Mehrfachregelung in DWR nachgewiesen. (orig.)Additional details
Publishing Information
- Imprint Title
- Advances in mathematical methods for the solution of nuclear engineering problems. Vol. 2
- Imprint Pagination
- 639 p.
- Journal Page Range
- p. 315-329.
- Report number
- INIS-mf--6714
Conference
- Title
- Joint ANS/ENS international topical meeting on advances in mathematical methods for the solution of nuclear engineering problems.
- Dates
- 27 - 29 Apr 1981.
- Place
- Munich, Germany, F.R.
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 13654098
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUTOMATION; DAILY VARIATIONS; DYNAMIC LOADS; FEEDBACK; FREQUENCY DEPENDENCE; LOAD MANAGEMENT; POWER DISTRIBUTION; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR CONTROL SYSTEMS; SIMULATION
- Descriptors DEC
- CONTROL SYSTEMS; COOLING SYSTEMS; MANAGEMENT; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; VARIATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS