SIMULATION OF THERMAL-HYDRAULIC PROCESS OF REACTOR IN HTR-PM
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.
Zhou Kefeng Zhou Yangping Ma Yuanle Sui Zhe Li Fu Dong Yujie
Tsinghua University Beijing, China
国际会议
18th International Conference on Nuclear Engineering(第18届国际核能工程大会 ICONE 18)
西安
英文
1-5
2010-05-17（万方平台首次上网日期，不代表论文的发表时间）