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Thermal-hydraulics characteristics of a heat pipe core of SAIRS-C

  • Hao Chun Zhang*
  • , Qian Ming Wei
  • , Wen Jiao
  • , Xiu Ting Liu
  • , De Zhuang Yin
  • *Corresponding author for this work

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

Heat pipe cooling space reactors are favored for their considerable application prospects. According to the design of the space-cooled reactor system, combined with the structural design scheme of the SAIRS-C heat pipe cooling space reactor, the heat pipe numerical model of the same structure and material as the literature experimental heat pipe was established, and the thermal hydraulic process of the core heat pipe was simulated. The pressure field of the working fluid, the velocity field distribution and the average temperature difference between the hot and cold ends of the heat pipe casing are obtained. The above data is then used to simulate the thermal characteristics of the fuel assembly and to address the core maximum temperature values to ensure safe operation of the system.

Original languageEnglish
Title of host publicationProceedings of the 27th International Conference on Nuclear Engineering, ICONE 2019 - "Nuclear Power Saves the World!"
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Electronic)9784888983051
StatePublished - 18 May 2019
Event27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019 - Tsukuba, Ibaraki, Japan
Duration: 19 May 201924 May 2019

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume2019-May

Conference

Conference27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
Country/TerritoryJapan
CityTsukuba, Ibaraki
Period19/05/1924/05/19

Keywords

  • Fuel element
  • Heat pipe
  • Heat pipe failure
  • Thermal characteristics

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