Analysis of the flow instability among channels of the OTSG in the naval craft NPP
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Hou Su-xia
Abstract
The instability occurring of the OTSG (Once-Through Steam Generator) in naval craft nuclear power plants is presented by the multivariable frequency domain theory. As concerning coupling interactions of the OTSG tubing, it is more accurate for analyzing the instability of OTSG compared to the common single variable method. A mathematical model for the system is derived from the fundamental equations by using the perturbation, Laplace-transform and the nodalization techniques. The stable boundary and parameters which influence the stability of the system are evaluated through computer simulation.
Kurzfassung
Die bei Durchlaufdampferzeugern (OTSG) in Schiffskernkraftwerken auftretenden Instabilitäten werden mit Hilfe der multivariaten Frequenzbereichstheorie dargestellt. In Bezug auf die Kopplungswechselwirkungen der OTSG Röhren, führt die Analyse der Instabilität des OTSG zu genaueren Ergebnissen, verglichen mit der Methode einzelner Variablen. Ein mathematisches Modell für das System wird aus den fundamentalen Gleichungen mit Hilfe der Störungstheorie, der Laplace-Transformation und von Nodalisierungsverfahren entwickelt. Die Randbedingungen und Parameter, die die Stabilität des Systems beeinflussen wurden mit Hilfe einer Computersimulation ausgewertet.
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© 2014, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Decomposition analysis of the sodium void reactivity of the Korean sodium-cooled fast reactor
- Flow accelerated corrosion study in feeder pipes
- Analysis of the flow instability among channels of the OTSG in the naval craft NPP
- Experimental investigation of the MSFR molten salt reactor concept
- Investigation of neutronic behavior in a CANDU reactor with different (Am, Th, 235U)O2 fuel matrixes
- Atomistic nano-scale 3D simulations about effects of Cr percentage on the molecular dynamics parameters of Fe-9–12% Cr alloys at fusion reactor temperature conditions
- On an analytical evaluation of the flux and dominant eigenvalue problem for the steady state multi-group multi-layer neutron diffusion equation
- A finite volume approach to the problem of heat transfer in axisymmetric annulus geometry with internal heating element using local analytical solution techniques
- CO2 doped γ-irradiated hydroxyapatite for EPR dosimetry
- An investigation of the effect of the upper beryllium reflector on the moderator temperature coefficient of reactivity of miniature neutron source reactors
