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.
- Nuclear Engineering Division
Simulation of Thermal-Hydraulic Process of Reactor in HTR-PM
Zhou, K, Zhou, Y, Ma, Y, Sui, Z, Li, F, & Dong, Y. "Simulation of Thermal-Hydraulic Process of Reactor in HTR-PM." Proceedings of the 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. pp. 187-191. ASME. https://doi.org/10.1115/ICONE18-29187
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