The modular high-temperature gas-cooled nuclear reactor (MHTGR) is seen as one of the best candidates for the next generation of nuclear power plants. China began to research the MHTGR technology at the end of the 1970s, and a 10 MWth pebble-bed high temperature reactor HTR-10 has been built. On the basis of the design and operation of the HTR-10, the high temperature gas-cooled reactor pebble-bed module (HTR-PM) project is proposed. One of the main differences between the HTR-PM and HTR-10 is that the ratio of height to diameter corresponding to the core of the HTR-PM is much larger than that of the HTR-10. Therefore it is not proper to use the point kinetics based model for control system design and verification. Motivated by this, a nodal neutron kinetics model for the HTR-PM is derived, and the corresponding nodal thermal-hydraulic model is also established. This newly developed nodal model can reflect not only the total or average information but also the distribution information such as the power distribution as well. Numerical simulation results show that the static precision of the new core model is satisfactory, and the trend of the transient responses is consistent with physical rules.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4929-3
PROCEEDINGS PAPER
A Nodal Dynamic Model for Control System Simulation of the HTR-PM Reactor Core Available to Purchase
Xiaojin Huang,
Xiaojin Huang
Tsinghua University, Beijing, China
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Liangju Zhang
Liangju Zhang
Tsinghua University, Beijing, China
Search for other works by this author on:
Zhe Dong
Tsinghua University, Beijing, China
Xiaojin Huang
Tsinghua University, Beijing, China
Liangju Zhang
Tsinghua University, Beijing, China
Paper No:
ICONE18-29055, pp. 611-618; 8 pages
Published Online:
April 8, 2011
Citation
Dong, Z, Huang, X, & Zhang, L. "A Nodal Dynamic Model for Control System Simulation of the HTR-PM Reactor Core." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 1. Xi’an, China. May 17–21, 2010. pp. 611-618. ASME. https://doi.org/10.1115/ICONE18-29055
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