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Bang, In Cheol
Nuclear Thermal-Hydraulics & Reactor Safety Lab
Research Interests
  • Nuclear Thermal-Hydraulics
  • Nuclear Safety
  • Nuclear System Design & Analysis
  • Nanofluids
  • Critical Heat Flux

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Design evaluation of the semi-prototype for the ITER blanket first wall qualification

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Title
Design evaluation of the semi-prototype for the ITER blanket first wall qualification
Author
Lee, Dong WonBae, Young DugKim, Suk KwonKim, Sun HoHong, Bong GuenBang, In Cheol
Issue Date
2010-09
Publisher
ELSEVIER SCIENCE SA
Citation
THIN SOLID FILMS, v.518, no.22, pp.6676 - 6681
Abstract
For the second qualification of the First Wall (FW) procurement of the International Thermonuclear Experimental Reactor (ITER), a semi-prototype of the FW has been designed with increased local surface heat flux up to 5 MW/m(2). With the given conditions, the new semi-prototype design was simulated with the commercial CFD code, the ANSYS-11. The results show that the semi-prototype temperature exceeds the melting temperature of Be, and the current design is required to be modified. In order to enhance cooling, a hypervapotron was added in the design and an analysis with the same code was performed. The results show that the temperature with the hypervapotron reduced by around 100 degrees C but it was still higher than the melting temperature of Be. The hypervapotron mock-up was fabricated and tested with a variance of inlet coolant flow rates and heat fluxes of up to 1.75 MW/m(2) using the second Korea Heat Load Test (KoHLT-2) facility, in which heat was loaded by a graphite heater through radiation heating. Wall and coolant temperatures were measured and compared with the simulation results. So far, there is a large difference between the experiments and the simulation, and a next experiment is being prepared.
URI
https://scholarworks.unist.ac.kr/handle/201301/3237
URL
http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=77956058423
DOI
10.1016/j.tsf.2010.03.149
ISSN
0040-6090
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