The dynamic performance of the Fueling Machine (F/M) Heavy Water (D2O) supply system for Wolsong Nuclear Power Plant (NPP) was evaluated using Modular Modeling System (MMS) computer code. Parametric study has been carried out to investigate the effects of dual common set pressure and the position change rate of series valve on the dynamic behavior of common header pressure and common bleed valve position during the mode changes of supply pressure. The results show that the introduction of the series valve position demand curve and the dual common header set pressure is effective to attenuate the overshoot of common header pressure during mode changes. This does not lead any adverse effects on the system performance of supply pressure control and heavy water supply to F/M during the mode changes. The dynamic evaluation results of the F/M D2O supply system will be used for the new control system parameter settings and help to relieve system operators’ burdens during the system operation.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3595-2
PROCEEDINGS PAPER
A Dynamic Performance Analysis on CANDU Fuel Handling System for Operational Improvement
Jeong Mann Kim,
Jeong Mann Kim
Korea Power Engineering Company, Inc., Daejon, Korea
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Byung Ryul Jung,
Byung Ryul Jung
Korea Power Engineering Company, Inc., Daejon, Korea
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Wan Kyu Park
Wan Kyu Park
Korea Hydro & Nuclear Power Company, Ltd., Kyongju, Korea
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Jeong Mann Kim
Korea Power Engineering Company, Inc., Daejon, Korea
Byung Ryul Jung
Korea Power Engineering Company, Inc., Daejon, Korea
Wan Kyu Park
Korea Hydro & Nuclear Power Company, Ltd., Kyongju, Korea
Paper No:
ICONE10-22091, pp. 29-36; 8 pages
Published Online:
March 4, 2009
Citation
Kim, JM, Jung, BR, & Park, WK. "A Dynamic Performance Analysis on CANDU Fuel Handling System for Operational Improvement." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 1. Arlington, Virginia, USA. April 14–18, 2002. pp. 29-36. ASME. https://doi.org/10.1115/ICONE10-22091
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