Simulation model of a nuclear power plant turbine
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A. Dutta
Abstract
A computer code “TURDYN” has been developed for prediction of high pressure and low pressure turbine torque under thermodynamic transient conditions. The model is based on the conservation laws of mass and energy. All the important components of turbine systems, e. g. high pressure turbine, low pressure turbine, feed heaters, reheater, moisture separator have been considered. The dynamic equations are solved simultaneously to obtain the stage pressure at various load conditions. The details of the mathematical formulation of the model and open loop responses for specific disturbances are presented.
Kurzfassung
Ein Rechencode „TURDYN“ wurde zur Vorhersage des Turbinen-Drehmoments bei hohem und niedrigem Druck unter thermodynamischen Transientenbedingungen entwickelt. Das Modell basiert auf den Gesetzen zur Erhaltung von Masse und Energie. Alle wichtigen Komponenten von Turbinensystemen wie z. B. Hochdruck- und Niederdruckturbinen, Vorwärmer, Zwischenüberhitzer, Separatoren wurden berücksichtigt. Die thermodynamischen Gleichungen werden gleichzeitig gelöst, um die Druckstufen unter verschiedenen Belastungsbedingungen zu erfassen. Die Einzelheiten der mathematischen Formulierung des Modells, sowie das Leerlaufverhalten bei speziellen Betriebsstörungen werden vorgestellt.
References
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© 2008, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Development and validation of the pressure surge computer code DYVRO mod. 3
- Simulation model of a nuclear power plant turbine
- Study on the thermal-hydraulics characteristics of a boiling two-phase natural circulation loop with nanofluids
- The effect of combination of different materials on neutron absorption in a nuclear research reactor spent fuel pool
- Re-evaluation of the criticality experiments of the “Otto Hahn Nuclear Ship” reactor
- Potential advantages and disadvantages of sequentially building small nuclear units instead of a large nuclear plant
- Radiological consequences of potential sabotage attack to storage casks on the ISFSI site
- Unified treatment of the P(λ)n approximation to solve the reflected slab criticality problem with strong anisotropy
- A comparative study on classical polynomial approximations to the transport equation in spherical media albedo problems
- Solution of half space and slab albedo problems for linearly anisotropic scattering with the modified FN method
- Study of the effect of anisotropic scattering on the critical slab problem in neutron transport theory using Chebyshev polynomials
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Development and validation of the pressure surge computer code DYVRO mod. 3
- Simulation model of a nuclear power plant turbine
- Study on the thermal-hydraulics characteristics of a boiling two-phase natural circulation loop with nanofluids
- The effect of combination of different materials on neutron absorption in a nuclear research reactor spent fuel pool
- Re-evaluation of the criticality experiments of the “Otto Hahn Nuclear Ship” reactor
- Potential advantages and disadvantages of sequentially building small nuclear units instead of a large nuclear plant
- Radiological consequences of potential sabotage attack to storage casks on the ISFSI site
- Unified treatment of the P(λ)n approximation to solve the reflected slab criticality problem with strong anisotropy
- A comparative study on classical polynomial approximations to the transport equation in spherical media albedo problems
- Solution of half space and slab albedo problems for linearly anisotropic scattering with the modified FN method
- Study of the effect of anisotropic scattering on the critical slab problem in neutron transport theory using Chebyshev polynomials
