Effects of bypass flow and power change and deviation on performance of thermal mixing structure of HTR-PM - 18424
Creators
- 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
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52072999
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BYPASSES; COMPUTERIZED SIMULATION; COOLANTS; HELIUM; HTGR TYPE REACTORS; MIXING; PERFORMANCE; REACTOR CORES; REGULATIONS; STEAM GENERATORS; TEST FACILITIES
- Descriptors DEC
- BOILERS; ELEMENTS; FLUIDS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; LAWS; NONMETALS; RARE GASES; REACTOR COMPONENTS; REACTORS; SIMULATION; VAPOR GENERATORS
Optional Information
- Notes
- 17 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)