Published November 2016 | Version v1
Book

Effects of bypass flow and power change and deviation on performance of thermal mixing structure of HTR-PM - 18424

  • 1. Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University - B211, Energy Science Building, Tsinghua University, Beijing 100084 (China)
  • 2. School of Aerospace, Tsinghua University - Yifu Science and Technology Building, Tsinghua University, Beijing 100084 (China)

Description

The temperature of bypass flow not flowing through the reactor core is obviously lower than that of the main coolant helium in a High Temperature Gas-cooled Reactor (HTGR). In addition, change and deviation of reactor power because of power regulation will introduce higher radial temperature difference of coolant helium from reactor to steam generator. In order to investigate the effects of bypass flow and power change and deviation on radial temperature difference of the helium flow entering the steam generator, model experiments and simulation calculations are proposed to evaluate the mixing performance of the thermal mixing structure at HTR-PM reactor core outlet. The experiments on Test Facility Hot Gas Mixing (TF-HGM) are carried out to observe the influences of bypass flow and reactor power deviation on mixing performance. In addition, some simulation calculations are conducted for the main mixing structure of the TF-HGM facility and the thermal mixing structure of HTR-PM. According to the results of experiments and simulation calculations, the maximum radial temperature difference at the outlet of the mixing structure fulfils the requirement by steam generator, less than 30 deg. C (#+-#15 deg. C), under all considered conditions. (authors)

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park, IL (United States)
Imprint Pagination
11 p.

Conference

Title
International Topical Meeting on High Temperature Reactor Technology
Acronym
HTR 2016
Dates
6-10 Nov 2016
Place
Las Vegas, NV (United States)

INIS

Optional Information

Notes
17 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)