Multiple regression approach to predict turbine-generator output for Chinshan nuclear power plant
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Yea-Kuang Chan
Abstract
The objective of this study is to develop a turbine cycle model using the multiple regression approach to estimate the turbine-generator output for the Chinshan Nuclear Power Plant (NPP). The plant operating data was verified using a linear regression model with a corresponding 95 percnt; confidence interval for the operating data. In this study, the key parameters were selected as inputs for the multiple regression based turbine cycle model. The proposed model was used to estimate the turbine-generator output. The effectiveness of the proposed turbine cycle model was demonstrated by using plant operating data obtained from the Chinshan NPP Unit 2. The results show that this multiple regression based turbine cycle model can be used to accurately estimate the turbine-generator output. In addition, this study also provides an alternative approach with simple and easy features to evaluate the thermal performance for nuclear power plants.
Kurzfassung
Ziel dieser Studie ist es, mit Hilfe der multiplen Regressionsanalyse ein Turbinenzyklusmodell zur Bestimmung der Turbinengeneratorleistung des Chinshan-Kernkraftwerks zu entwickeln. Die Betriebsdaten wurden mit Hilfe eines linearen Regressionsmodells mit 95 percnt; Konfidenzintervall verifiziert. In dieser Studie wurden die wichtigsten Parameter als Input für das Turbinenzyklusmodell ausgewählt. Das vorgestellte Modell wurde zur Bestimmung der Turbinengeneratorleistung verwendet. Die Leistungsfähigkeit des vorgeschlagenen Turbinenzyklusmodells wurde mit Hilfe der Betriebsdaten der Einheit 2 des Chinshan-Kernkraftwerks nachgewiesen. Die Ergebnisse zeigen, dass das Turbinenzyklusmodell zur genauen Bestimmung der Turbinengeneratorleistung verwendet werden kann. Die Studie liefert auch einen alternativen Ansatz mit einfachen Merkmalen zur Bewertung der thermischen Leistung von Kernkraftwerken.
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© 2017, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- CANDU pressure tube leak detection by annulus gas dew point measurement: a critical review
- Multiple regression approach to predict turbine-generator output for Chinshan nuclear power plant
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- Analysis of the optimal fuel composition for the Indonesian experimental power reactor
- Radiogenic lead from poly-metallic thorium ores as a valuable material for advanced nuclear facilities
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- Font Attributes based Text Steganographic algorithm (FATS) for communicating images: A nuclear power plant perspective
- Size control synthesis and characterization of ZnO nanoparticles and its application as ZnO-water based nanofluid in heat transfer enhancement in light water nuclear reactor
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- Exact solution of the neutron transport equation in spherical geometry
- Technical Notes/Technische Mitteilungen
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- CANDU pressure tube leak detection by annulus gas dew point measurement: a critical review
- Multiple regression approach to predict turbine-generator output for Chinshan nuclear power plant
- 10.3139/124.110675
- Development of a parallel processing couple for calculations of control rod worth in terms of burn-up in a WWER-1000 reactor
- Simulation of protected and unprotected loss of flow transients in a WWER-1000 reactor based on the Drift-Flux Model
- Sensitivity analysis for CORSOR models simulating fission product release in LOFT-LP-FP-2 severe accident experiment
- Analysis of the optimal fuel composition for the Indonesian experimental power reactor
- Radiogenic lead from poly-metallic thorium ores as a valuable material for advanced nuclear facilities
- The effects of applying silicon carbide coating on core reactivity of pebble-bed HTR in water ingress accident
- Font Attributes based Text Steganographic algorithm (FATS) for communicating images: A nuclear power plant perspective
- Size control synthesis and characterization of ZnO nanoparticles and its application as ZnO-water based nanofluid in heat transfer enhancement in light water nuclear reactor
- Nuclear characteristics of epoxy resin as a space environment neutron shielding
- Exact solution of the neutron transport equation in spherical geometry
- Technical Notes/Technische Mitteilungen
- Determination of self-attenuation correction factor for lichen samples by using gamma-ray spectrometry
