An active residual heat removal process is required by the gas-cooled reactor pebble-bed module plant being constructed in China, in order to improve the economical performance of the plant by shortening the restart duration. This process makes use of steam generator and start-up loop as heat sink, whose structure may suffer cold/heat shock while the sudden load of coolant or hot helium at the beginning. To achieve safety and reliability, transient analysis was carried out based on a one-dimensional mathematical model for steam generator and steam pipe of start-up loop. The calculation results show that steam generator should be discharged and pre-cooled; otherwise, boiling will arise and introduce a cold shock to the boiling tubes and tube sheet when coolant began to circulate prior to the helium. Additionally, in avoiding heat shock caused by the sudden load of helium, the helium circulation should be restricted to start with an extreme low flow rate; meanwhile, the coolant of steam generator (water) should have flow rate as large as possible. Finally, a four-step procedure with pre-cooling process of steam generator was recommended; sensitive study for the main parameters was conducted.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5579-9
PROCEEDINGS PAPER
Transient Analysis of Active Residual Heat Removal Process for HTR-PM
Hongye Zhu,
Hongye Zhu
Tsinghua University, Beijing, China
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Xingtuan Yang,
Xingtuan Yang
Tsinghua University, Beijing, China
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Huaiming Ju,
Huaiming Ju
Tsinghua University, Beijing, China
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Shengyao Jiang
Shengyao Jiang
Tsinghua University, Beijing, China
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Hongye Zhu
Tsinghua University, Beijing, China
Xingtuan Yang
Tsinghua University, Beijing, China
Huaiming Ju
Tsinghua University, Beijing, China
Shengyao Jiang
Tsinghua University, Beijing, China
Paper No:
ICONE21-15448, V002T03A022; 8 pages
Published Online:
February 7, 2014
Citation
Zhu, H, Yang, X, Ju, H, & Jiang, S. "Transient Analysis of Active Residual Heat Removal Process for HTR-PM." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors. Chengdu, China. July 29–August 2, 2013. V002T03A022. ASME. https://doi.org/10.1115/ICONE21-15448
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