This paper describes the development of a compact engineering simulator of Pebble-bed Modular High Temperature Gas-cooled Reactor (HTR-PM) by embedding THERMIX code into the vPower simulation environment. The compact engineering simulator consists of modules for two reactors, two steam generators and entire secondary loop system for power generation with a water-steam Rankin cycle. Two THERMIX modules are employed to simulate the two primary loops corresponding to the two reactors in the HTR-PM respectively. Then, the vPower synchronizes the two THERMIX modules in executing simulation to such two reactor module-structures of HTR-PM. The simulation modules for secondary loop and human machine interface are mainly developed with intrinsic models of vPower simulation platform. Current simulation results are in good agreement with the design values and safety analysis results of HTR-PM. The compact HTR-PM engineering simulator will be improved and validated for safe analysis, procedure development and design change verification.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4930-9
PROCEEDINGS PAPER
Compact Engineering Simulator for HTR-PM by Embedding THERMIX Code in vPower Simulation Platform
Yangping Zhou,
Yangping Zhou
Tsinghua University, Beijing, China
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Zhiwei Zhou,
Zhiwei Zhou
Tsinghua University, Beijing, China
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Fu Li
Fu Li
Tsinghua University, Beijing, China
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Qiang Gao
Tsinghua University, Beijing, China
Yangping Zhou
Tsinghua University, Beijing, China
Zhiwei Zhou
Tsinghua University, Beijing, China
Zhe Sui
Tsinghua University, Beijing, China
Yuanle Ma
Tsinghua University, Beijing, China
Fu Li
Tsinghua University, Beijing, China
Paper No:
ICONE18-29437, pp. 543-549; 7 pages
Published Online:
April 8, 2011
Citation
Gao, Q, Zhou, Y, Zhou, Z, Sui, Z, Ma, Y, & Li, F. "Compact Engineering Simulator for HTR-PM by Embedding THERMIX Code in vPower Simulation Platform." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 2. Xi’an, China. May 17–21, 2010. pp. 543-549. ASME. https://doi.org/10.1115/ICONE18-29437
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