DocumentCode
3775521
Title
Thermal-hydraulic analysis for conceptual design of Korean HCCR TBM-set
Author
Dong Won Lee; Hyung Gon Jin; Eo Hwak Lee; Suk-Kwon Kim; Jae Sung Yoon; Kyu In Shin; Seungyon Cho
Author_Institution
Korea Atomic Research Institute, Daejeon, Republic of Korea
fYear
2015
fDate
5/1/2015 12:00:00 AM
Firstpage
1
Lastpage
4
Abstract
Korea has designed a Helium Cooled Ceramic Reflector Test Blanket Module (HCCR TBM) including TBMshield, which is called TBM-set to be tested in ITER. Thermalhydraulic analyses are performed with conventional CFD code, ANSYS-CFX v14.5 for Electro-Magnetic Module (EM-TBM) and INTegral Module (INT-TBM) including TBM-shield, respectively. With the same model and meshes according to the ITER operation conditions of H/He and D-T phases, respectively, temperature distribution, flow rate and pressure drop are investigated to meet the design requirements and the temperature data are directly provided to mechanical analysis.
Keywords
"Heating","Coolants","Temperature distribution","Plasma temperature","Thermomechanical processes"
Publisher
ieee
Conference_Titel
Fusion Engineering (SOFE), 2015 IEEE 26th Symposium on
Electronic_ISBN
2155-9953
Type
conf
DOI
10.1109/SOFE.2015.7482299
Filename
7482299
Link To Document