CFD aided design of the experimental helium loop for VHTR simulation
Creators
- 1. Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of)
Description
A medium-scale helium loop for simulating a VHTR (Very High Temperature Reactor) is now under construction in KAERI (Korea Atomic Energy Research Institute). Two electric heaters of the test helium loop heat the helium fluid up to 950°C at a pressure of 1 ~ 9MPa. To optimize the design specifications of the experimental helium loop, conjugate heat transfer in the high-temperature helium heater was analyzed by using CFD (Computational Fluid Dynamics) simulation. The main factors tested in this CFD analysis were the effects of turbulence, radiation, gravity, and geometrical configuration of the heater. From the analysis results, the optimum design configuration was selected confirming that thermal characteristics of the heater well meet the design requirements. In this study, the interrelated effects of buoyancy forces and radiation heat transfer on the geometrical configuration were closely investigated. It was concluded that the buoyancy effects on the helium flows of the heater would be suppressed by the radiation heat transfer inside the heating channel. Various emissivity values of the reflector material emissivity were also tested. Gravity had greater effects on the temperature distribution for the lower emissivity, but the maximum temperature variations due to the emissivity changes from 0.1 to 0.9 were limited to within a few tens of degrees. Finally, more detailed analyses on the HTH of the medium scale helium loop including the spacers were performed and it is confirmed that the thermal-fluidic characteristics of the HTH satisfied the design requirements. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 978-1-926773-05-6
- Imprint Title
- The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)
- Imprint Pagination
- 766 Megabytes
- Journal Page Range
- [19 p.]
Conference
- Title
- 14. International Topical Meeting on Nuclear Reactor Thermalhydraulics
- Acronym
- NURETH-14
- Dates
- 25-30 Sep 2011
- Place
- Toronto, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 47071143
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; COOLANT LOOPS; FLUID MECHANICS; HEAT TRANSFER; HELIUM; TURBULENCE; VHTR REACTOR
- Descriptors DEC
- COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FLUIDS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MECHANICS; NONMETALS; POWER REACTORS; RARE GASES; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; THERMAL REACTORS
Optional Information
- Notes
- Paper NURETH14-167, 10 refs., 6 tabs., 12 figs.