In nuclear plants, feedwater flow is utilized to calculate the heat input to the Nuclear Steam Supply System (NSSS). The heat input, in conjunction with a heat balance around the reactor, is used to calculate the reactor core thermal power. Since a calibrated flow nozzle is used to measure feedwater flow and, the calibration assumes a clean flow section with no fouling, any deposits or fouling of the flow nozzle will result in errors in flow measurement, causing the flow to read high. This would result in a calculated reactor power higher than the true value and an attendant loss in plant capacity. The paper presents the methodology and heat balance techniques used in diagnosing the existence of feedwater flow nozzle fouling and in quantifying the capacity loss. The paper provides recommendations on how to monitor performance for tell-tale signs of feedwater flow nozzle fouling and steps to take for corrective action.
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International Joint Power Generation Conference collocated with TurboExpo 2003
June 16–19, 2003
Atlanta, Georgia, USA
Conference Sponsors:
- Power Division
ISBN:
0-7918-3692-4
PROCEEDINGS PAPER
Heat Balance Techniques for Diagnosing and Evaluating Feedwater Flow Nozzle Fouling in Nuclear Plants
Komandur S. Sunder Raj
Komandur S. Sunder Raj
Power & Energy Systems Services, Oradell, NJ
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Komandur S. Sunder Raj
Power & Energy Systems Services, Oradell, NJ
Paper No:
IJPGC2003-40005, pp. 223-231; 9 pages
Published Online:
December 17, 2008
Citation
Sunder Raj, KS. "Heat Balance Techniques for Diagnosing and Evaluating Feedwater Flow Nozzle Fouling in Nuclear Plants." Proceedings of the International Joint Power Generation Conference collocated with TurboExpo 2003. 2003 International Joint Power Generation Conference. Atlanta, Georgia, USA. June 16–19, 2003. pp. 223-231. ASME. https://doi.org/10.1115/IJPGC2003-40005
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