Abstract
For the 1308 MWe NPP Müilheim-Kärlich, with a two loop nuclear steam supply system and once-through steam generators a computer code for the analysis of operational transients and control system optimization has been developed. After completion of startup testing a comparison of code results against field data was made. The comparison shows good agreement and demonstrates that the scope of the simulation and the mathematical models meet the requirements of a best estimate analysis tool for operational transients.
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References
R. Bieselt, P. Wirtz: “Der BBR-Druckwasserreaktor mit Geradrohrdampferzeuger” Sonderdruck aus VGB-Kernkraftwerks-Seminar 1978
R. T. Lahey, F. J. Moody: “The Thermal-Hydraulics of a Boiling Water Nuclear Reactor” American Nuclear Society 1977
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© 1987 Springer-Verlag, Berlin, Heidelberg
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Breiling, G. (1987). Nuclear Power Plant Transient Analysis. In: Heller, M.R. (eds) Nuclear Simulation. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-83221-5_5
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DOI: https://doi.org/10.1007/978-3-642-83221-5_5
Publisher Name: Springer, Berlin, Heidelberg
Print ISBN: 978-3-642-83223-9
Online ISBN: 978-3-642-83221-5
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