This work developed an Advanced Boiling Water Reactor (ABWR) feedwater pump and controller model, which was incorporated into Personal Computer Transient Analyzer (PCTran)-ABWR, a nuclear power plant simulation code. The feedwater pump model includes three turbine-driven feedwater pumps and one motor-driven feedwater pump. The feedwater controller includes a one-element / three-element water level controller and a specific feedwater speed controller for each feedwater pump. The performance tests, including inadvertent closure of all turbine control valves and one feedwater pump trip at 100% power, demonstrate the feasibility of dynamic response of incorporated model. Furthermore, a diversity and defense-in-depth analysis is performed to demonstrate the feasibility for motor-driven feedwater pump as an Emergency Core Cooling System (ECCS) automatic diverse back-up. In Lungmen Nuclear Power Plant (NPP), a diverse manual initiation means for the High Pressure Core Flooder (HPCF) loop C is designed as the back-up of digitalized Engineered Safety Features Actuation System (ESFAS). If the Motor-Driven Feedwater Pump (MDFWP) can be an automatic digital diverse back-up for ESFAS, Lungmen NPP would be more robust to defend against software common cause failure (CCF).
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4353-6
PROCEEDINGS PAPER
Development and D3 Application of ABWR Feedwater System Model Available to Purchase
Hui-Wen Huang,
Hui-Wen Huang
Institute of Nuclear Energy Research, Longtan, Taiwan
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Chunkuan Shih,
Chunkuan Shih
National Tsing Hua University, Hsinchu, Taiwan
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Hung-Chih Hung,
Hung-Chih Hung
National Tsing Hua University, Hsinchu, Taiwan
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Kai-Lan Chang,
Kai-Lan Chang
National Tsing Hua University, Hsinchu, Taiwan
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Shu-Chuan Chen,
Shu-Chuan Chen
National Tsing Hua University, Hsinchu, Taiwan
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Yu-Jen Pan,
Yu-Jen Pan
Institute of Nuclear Energy Research, Longtan, Taiwan
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Mao-Sheng Tseng,
Mao-Sheng Tseng
Institute of Nuclear Energy Research, Longtan, Taiwan
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Ming-Huei Chen,
Ming-Huei Chen
Institute of Nuclear Energy Research, Longtan, Taiwan
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Tsung-Chieh Cheng
Tsung-Chieh Cheng
Institute of Nuclear Energy Research, Longtan, Taiwan
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Hui-Wen Huang
Institute of Nuclear Energy Research, Longtan, Taiwan
Chunkuan Shih
National Tsing Hua University, Hsinchu, Taiwan
Hung-Chih Hung
National Tsing Hua University, Hsinchu, Taiwan
Kai-Lan Chang
National Tsing Hua University, Hsinchu, Taiwan
Shu-Chuan Chen
National Tsing Hua University, Hsinchu, Taiwan
Yu-Jen Pan
Institute of Nuclear Energy Research, Longtan, Taiwan
Mao-Sheng Tseng
Institute of Nuclear Energy Research, Longtan, Taiwan
Ming-Huei Chen
Institute of Nuclear Energy Research, Longtan, Taiwan
Tsung-Chieh Cheng
Institute of Nuclear Energy Research, Longtan, Taiwan
Paper No:
ICONE17-75104, pp. 105-114; 10 pages
Published Online:
February 25, 2010
Citation
Huang, H, Shih, C, Hung, H, Chang, K, Chen, S, Pan, Y, Tseng, M, Chen, M, & Cheng, T. "Development and D3 Application of ABWR Feedwater System Model." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance. Brussels, Belgium. July 12–16, 2009. pp. 105-114. ASME. https://doi.org/10.1115/ICONE17-75104
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