Thermohydraulic phenomena of a steam-water natural-circulation (SWNC) system are very complicated, particularly, during its start-up and shutdown. Its performance strongly depends on the circulation inside it. Accurate quantification of the flow, void fraction, two-phase level, boiling boundary, etc., is difficult at both steady state and transient states like load variation, start-up, and shutdown. Attempts have been made to develop a high-fidelity thermohydraulic model (five-equation scheme) that caters to nonhomogeneous and thermal nonequilibrium flow to derive the dynamic effect of heating rate on the performance of the SWNC loop of steam generator of an Indian nuclear reactor during steaming-up period. The proposed work also attempts to predict boiling height, flow reversal, and density-wave oscillation (DWO). The boiling channel of the SWNC loop is modeled based on the moving boundary analysis using finite volume method. In this moving boundary problem, both control volumes of single-phase zone and two-phase zone change with time. Numerical results have been presented in this paper. The results indicate that both circulation flow variation and two-phase level variation in steam drum have strong dependency on void fraction in the boiling channel. Flow-reversal phenomenon is identified during the initial stage of boiling. Two-phase swelling and collapse that occur during the start-up are predicted. Above a critical heating rate, DWO has been observed. All these phenomena have been explained.
Skip Nav Destination
e-mail: swapanparuya@rediffmail.com
e-mail: pinaki̱che@yahoo.com
Article navigation
Research Papers
A Moving Boundary Analysis for Start-Up Performance of a Nuclear Steam Generator
S. Paruya,
S. Paruya
Department of Chemical Engineering,
e-mail: swapanparuya@rediffmail.com
Haldia Institute of Technology
, Haldia 721 657, India
Search for other works by this author on:
P. Bhattacharya
P. Bhattacharya
Department of Chemical Engineering,
e-mail: pinaki̱che@yahoo.com
Jadavpur University
, Kolkata 700 032, India
Search for other works by this author on:
S. Paruya
Department of Chemical Engineering,
Haldia Institute of Technology
, Haldia 721 657, Indiae-mail: swapanparuya@rediffmail.com
P. Bhattacharya
Department of Chemical Engineering,
Jadavpur University
, Kolkata 700 032, Indiae-mail: pinaki̱che@yahoo.com
J. Fluids Eng. May 2008, 130(5): 051303 (11 pages)
Published Online: May 5, 2008
Article history
Received:
March 8, 2007
Revised:
November 30, 2007
Published:
May 5, 2008
Citation
Paruya, S., and Bhattacharya, P. (May 5, 2008). "A Moving Boundary Analysis for Start-Up Performance of a Nuclear Steam Generator." ASME. J. Fluids Eng. May 2008; 130(5): 051303. https://doi.org/10.1115/1.2911684
Download citation file:
Get Email Alerts
Cited By
Experimental Investigation of the Effect of Rake on a Bluff Body Equipped With a Diffuser
J. Fluids Eng (April 2025)
Related Articles
Effect of Pressure With Wall Heating in Annular Two-Phase Flow
J. Fluids Eng (January,2003)
Analysis of Solid–Liquid Phase Change Under Pulsed Heating
J. Heat Transfer (March,2007)
Vibration of a Tube Bundle in Two-Phase Freon
Cross-Flow
J. Pressure Vessel Technol (November,1995)
Flow Visualization of Submerged Steam Jet in Subcooled Water
J. Heat Transfer (February,2016)
Related Proceedings Papers
Related Chapters
Scope of Section I, Organization, and Service Limits
Power Boilers: A Guide to the Section I of the ASME Boiler and Pressure Vessel Code, Second Edition
Thermal Design Guide of Liquid Cooled Systems
Thermal Design of Liquid Cooled Microelectronic Equipment
Liquid Cooled Systems
Thermal Management of Telecommunications Equipment