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Bang, In Cheol
Nuclear Thermal-Hydraulics & Reactor Safety Lab
Research Interests
  • Nuclear Thermal-Hydraulics

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Thermal hydraulic test with 6 MPa nitrogen gas loop for developing the Korean He cooled test blanket

Cited 2 times inthomson ciCited 2 times inthomson ci
Title
Thermal hydraulic test with 6 MPa nitrogen gas loop for developing the Korean He cooled test blanket
Author
Lee, Dong WonBae, Young DugKim, Suk KwonHong, Bong GuenKim, Chan SuHong, Sung DeokTak, Nam IlBang, In Cheol
Keywords
ANSYS-CFX V11; GAMMA; He coolant; ITER; TBM; Thermal hydraulics
Issue Date
201012
Publisher
ELSEVIER SCIENCE SA
Citation
FUSION ENGINEERING AND DESIGN, v.85, no.10-12, pp.2160 - 2164
Abstract
In considering the requirements for a DEMO-relevant blanket concept, Korea (KO) has proposed a Helium Cooled Molten Lithium (HCML) Test Blanket Module (TBM) for testing in the International Thermonuclear Experimental Reactor (ITER). The performance analysis for thermal-hydraulics and safety analysis for an accident caused by loss of a coolant for the KO TBM has been carried out with a commercial CFD code, ANSYS-CFX V11 and system code, GAMMA (GAs Multicomponent Mixture Analysis). In order to verify the codes, a basic thermal-hydraulic test with a high pressure nitrogen gas loop up to 6 MPa pressure and 950 degrees C temperature was performed. In the experiment, single TBM First Wall (FW) mock-up made from the same material as the KO TBM, Ferritic Martensitic Steel, was used and the test was performed under the conditions of pressures of 20 and 36 bar and flow rates of 0.75 and 0.92 kg/min. As one-side of the mock-up was heated to 230 degrees C, the wall temperatures were measured by installed thermocouples. The measured temperatures show a strong parity with codes' results simulated with the same test conditions. An additional test with higher pressure and temperature has been prepared for the future.
URI
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DOI
http://dx.doi.org/10.1016/j.fusengdes.2010.08.024
ISSN
0920-3796
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