Analysis of the instability of OTSG of movable nuclear power devices by using the multivariable frequency domain method
-
S.-X. Hou
Abstract
A new method for analyzing the problem of the thermal-hydrodynamic instability of OTSG (Once-Through Steam Generator) of movable nuclear power devices is presented in this paper. The method is based on multivariable frequency domain theory and is more efficient for analyzing the instability of OTSG with coupling interactions and complicated boundary conditions than the usually used single variable method. A mathematical model for the system is derived from the fundamental equations by using perturbation, Laplace-transform and the nodalization techniques. The stable boundary and parametric effects on the stability of the system are evaluated with a computer code. Numerical examples are given and the predictions of the model are in good agreement with the experimental results.
Kurzfassung
Eine neue Methode zur Analyse von thermo-hydrodynamischen Instabilitäten von OTSG-Dampferzeugern beweglicher kerntechnischer Einrichtungen wird in dieser Arbeit vorgestellt. Die Methode basiert auf der multivariablen Frequenz-Domain-Theorie und ist effektiver für die Analyse der Instabilität von OTSG-Dampferzeugern mit Kopplungswechselwirkung und komplizierten Randbedingungen als die üblicherweise verwendete singlevariable Methode. Ein mathematisches Modell für das System wurde abgeleitet von den fundamentalen Gleichungen mit Hilfe von Pertubation, Laplace-Transformation und Nodalisierungsverfahren. Die Stabilität des Systems wird mit Hilfe eines Computercodes ausgewertet. Numerische Beispiele werden gegeben und die Vorhersagen des Modells stimmen gut überein mit den experimentellen Ergebnissen.
References
1 Boure, J. A.; Bergles, A. E.: Review of two-phase flow instability. Nuclear Engineering and Design25 (1973) 16510.1016/0029-5493(73)90043-5Suche in Google Scholar
2 Lee, J. D.; Pan, C.: Dynamics of multiple parallel boiling channel systems with forced flows. Nuclear Engineering and Design192 (1999) 31Suche in Google Scholar
3 Romberg, T. M.: Flow stability analysis of two-phase heat transfer circuits and multi-channel systems. Two-Phase Flow and Heat Transfer Conference: China-U.S. Progress, Beijing, China, 1985, p. 677Suche in Google Scholar
4 Zuber, N.: In two-phase flow dynamics, EURATOM, 1967, Vol. 4288, p. 1071Suche in Google Scholar
5 Murata, H.; Sawada, K.: Natural circulation characteristics of a marine reactor in rolling motion and heat transfer in the core. Nuclear Engineering and Design215 (2002) 69Suche in Google Scholar
6 Aritomi, M.; Aoki, S.; Inoue, A.: Instabilities in parallel of forced-convection boiling upflow system. Nuclear Science and Technology14 (1977) 22Suche in Google Scholar
7 Lee, J. D.; Pan, C.: Nonlinear stability analysis for multiple parallel boiling channels with forced flows. National Heat Transfer Conference, ASME, HTD, 1996, Vol. 326, p. 341–346Suche in Google Scholar
8 Munoz, J. L.; Rosello, O.; Miro, R.: Coupling of density wave oscillations in parallel channels with high order model kinetics: application to BWR out of phase oscillations, Annals of Nuclear Energy27 (2000) 1345Suche in Google Scholar
9 Lee, J. D.; Pan, C.: Dynamic analysis of model multiple nuclear-coupled boiling channels based on a multi-point reactor. Nuclear Engineering and Design235 (2005) 2358Suche in Google Scholar
10 Geping, W.; Suizheng, Q.: Experimental research on flow instability in vertical narrow annuli. Nuclear Science and Techniques18 (2007) 247Suche in Google Scholar
11 Jinliang, X.; Jijun, Z.: Static and dynamic flow instability of a parallel micro-channel heat sink at high heat fluxes. Energy Conversion and Management46 (2005) 313Suche in Google Scholar
12 Qu, W. L.; Mudawar, I.: Flow boiling heat transfer in two-phase micro-channel heat sinks. Heat and Mass Transfer46 (2003) 2755Suche in Google Scholar
13 Ruan, Y. Q.; Fu, L. Z.: Proc. Analysis of thermal-hydrodynamic instability of steam generator. IFAC, Philadelphia, September 16–18, 1986, p. 124–130Suche in Google Scholar
© 2010, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Adaptation of the FEMAXI-6 code and RBMK fuel rods model testing employing the best estimate approach
- In-reactor measurements of fuel centerline temperature variation during power change
- Pertinence of tests used for conformity assessments of fire resistance of nuclear power plant components – opinion of several institutions in Europe
- Analysis of the instability of OTSG of movable nuclear power devices by using the multivariable frequency domain method
- Steady state thermal hydraulic calculations for MTR plate-type research reactors
- Production cross sections of medical 110,111In radionuclides
- Nuclear level density parameters of some largely deformed nuclei of medical radionuclides in low-lying collective excitation modes
- A discrete ordinates operator for the diffuse transmission of a mixed neutron beam through a multilayered medium
- Kritikalitätssicherheit der Endlagerung ausgedienter Kernbrennstoffe
- Technical Notes/Technische Mitteilungen
- Methods for thin foil thickness determination by using alpha spectroscopy
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Adaptation of the FEMAXI-6 code and RBMK fuel rods model testing employing the best estimate approach
- In-reactor measurements of fuel centerline temperature variation during power change
- Pertinence of tests used for conformity assessments of fire resistance of nuclear power plant components – opinion of several institutions in Europe
- Analysis of the instability of OTSG of movable nuclear power devices by using the multivariable frequency domain method
- Steady state thermal hydraulic calculations for MTR plate-type research reactors
- Production cross sections of medical 110,111In radionuclides
- Nuclear level density parameters of some largely deformed nuclei of medical radionuclides in low-lying collective excitation modes
- A discrete ordinates operator for the diffuse transmission of a mixed neutron beam through a multilayered medium
- Kritikalitätssicherheit der Endlagerung ausgedienter Kernbrennstoffe
- Technical Notes/Technische Mitteilungen
- Methods for thin foil thickness determination by using alpha spectroscopy
