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Simulation of Thermal-Hydraulic Process of Reactor in HTR-PM

[+] Author Affiliations
Kefeng Zhou, Yangping Zhou, Yuanle Ma, Zhe Sui, Fu Li, Yujie Dong

Tsinghua University, Beijing, China

Paper No. ICONE18-29187, pp. 187-191; 5 pages
  • 18th International Conference on Nuclear Engineering
  • 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B
  • Xi’an, China, May 17–21, 2010
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-4932-3
  • Copyright © 2010 by ASME


This paper provides a discussion of the model development status and verifications for the components used in the Reactor Thermal-Hydraulic model for the Full-Scale Simulator (FSS) of the High Temperature Gas-cooled Reactor Pebble-bed Module (HTR-PM). Heat transfer network and thermal-hydraulic network are adopted to simulate the thermal-hydraulic process of reactor of HTR-PM. Due to the First of a Kind Engineering nature and lack of reference plant data, model verification will mainly focus on benchmarking the model configurations against test cases performed by HTR-PM design code THERMIX in future.

Copyright © 2010 by ASME



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