Simulation of load following mode of operation for a natural circulation pressure tube type BWR
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R. Kumar
Abstract
A new nuclear power reactor under design study is a vertical pressure tube type boiling light water cooled and heavy water moderated. One of the passive design features of this reactor is the heat removal through natural circulation of primary coolant at all power level with no primary coolant pumps. Nuclear plants are mainly base load units, but the proposed plant with various advance features has to operate in load following mode i.e. Reactor follows Turbine (in a limited range). In this mode, any alteration in turbine load results in the steam pressure change. The steam pressure error is fed to the Reactor Regulating System (RRS), which changes the reactor power to control the system pressure. To study this mode of plant operation, a plant simulation model with the feedbacks from various controllers has been developed using the RELAP5 code. This integrated plant model has been used for simulating the load-varying scenario for a change in plant load. All the process dynamics, modeling, design verification and performance issues are discussed in this paper.
Kurzfassung
Ein neuer Kernreaktor, der zur Zeit im Rahmen einer Auslegungsstudie untersucht wird, ist ein Druckröhrenreaktor mit vertikal verlaufenden Kühlkanälen, mit leichtem Wasser als Kühlmittel und schwerem Wasser als Moderator. Eines der passiven Sicherheitsmerkmale dieses Reaktors ist die Wärmeabfuhr durch Naturumlauf des Primärkühlmittels bei allen Leistungsstufen ohne Pumpen im Primärkühlmittelkreislauf. Der vorgeschlagene Reaktor hat verschiedene fortschrittliche Merkmale und arbeitet in Lastwechsel-Betriebsweise, d.h. im „reactor-follows-turbine“ Modus (im begrenzten Rahmen). Bei dieser Betriebsweise führt jede Änderung der Turbinenlast zu einer Änderung des Dampfdruckes. Der Dampfdruckfehler wird dem „Reactor Regulating System (RRS)“ zugeführt, das die Leistung des Reaktors ändert, um so den Druck im System zu kontrollieren. Zur Untersuchung dieser Betriebsweise wurde mit Hilfe des RELAP5 Codes ein Anlagensimulationsmodell entwickelt mit Feedback aus verschiedenen Kontrollsystemen. Dieses integrierte Anlagenmodell wurde verwendet zur Simulation des Lastwechsel-Szenarios für eine Änderung der Anlagenlast. Die Prozessdynamik, die Modellierung, die Auslegungs-Verifizierung und Ausführungsfragen werden in diesem Beitrag diskutiert.
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© 2011, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Stress analyses for reactor pressure vessels by the example of a product line '69 Boiling Water Reactor
- Multiple condensation induced water hammer events, experiments and theoretical investigations
- Simulation of load following mode of operation for a natural circulation pressure tube type BWR
- CANDU fuel elements behaviour in the load following tests
- Local heat transfer coefficient near the spacer grids
- Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module
- Investigations of bi-directional flow behaviour in presence of a large vertical opening in a fire compartment
- CANDU reactors with reactor grade plutonium/thorium carbide fuel
- Novel method to produce 109Cd via proton irradiation of electroplated silver on a gold-coated copper backing
- Technical Notes/Technische Mitteilungen
- Atmospheric dispersion of accidental release of radioactive gases from high enriched and low enriched fuel of Miniature Neutron Source Reactors (MNSR)
- Fuel burnup of modified fuel assembly configurations for a small medical reactor
- Determination of natural uranium, thorium and radium isotopes in water and soil samples by alpha spectroscopy
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Stress analyses for reactor pressure vessels by the example of a product line '69 Boiling Water Reactor
- Multiple condensation induced water hammer events, experiments and theoretical investigations
- Simulation of load following mode of operation for a natural circulation pressure tube type BWR
- CANDU fuel elements behaviour in the load following tests
- Local heat transfer coefficient near the spacer grids
- Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module
- Investigations of bi-directional flow behaviour in presence of a large vertical opening in a fire compartment
- CANDU reactors with reactor grade plutonium/thorium carbide fuel
- Novel method to produce 109Cd via proton irradiation of electroplated silver on a gold-coated copper backing
- Technical Notes/Technische Mitteilungen
- Atmospheric dispersion of accidental release of radioactive gases from high enriched and low enriched fuel of Miniature Neutron Source Reactors (MNSR)
- Fuel burnup of modified fuel assembly configurations for a small medical reactor
- Determination of natural uranium, thorium and radium isotopes in water and soil samples by alpha spectroscopy
