Thermal-Hydraulic Analysis for Conceptual Design of Korean HCCR TBM Set

With a conceptual design of Korean helium-cooled ceramic reflector test blanket module (TBM), including TBM shield for testing in ITER, thermal-hydraulic analyses are performed with a conventional CFD code, ANSYS-CFX v14.5, for the electromagnetic module and the integral module, including the TBM sh...

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Veröffentlicht in:IEEE transactions on plasma science 2016-09, Vol.44 (9), p.1571-1575
Hauptverfasser: Lee, Dong-Won, Park, Seong Dae, Jin, Hyung Gon, Lee, Eo Hwak, Kim, Suk-Kwon, Yoon, Jae Sung, Shin, Kyu In, Cho, Seungyon
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container_end_page 1575
container_issue 9
container_start_page 1571
container_title IEEE transactions on plasma science
container_volume 44
creator Lee, Dong-Won
Park, Seong Dae
Jin, Hyung Gon
Lee, Eo Hwak
Kim, Suk-Kwon
Yoon, Jae Sung
Shin, Kyu In
Cho, Seungyon
description With a conceptual design of Korean helium-cooled ceramic reflector test blanket module (TBM), including TBM shield for testing in ITER, thermal-hydraulic analyses are performed with a conventional CFD code, ANSYS-CFX v14.5, for the electromagnetic module and the integral module, including the TBM shield. With the same model and meshes, according to the ITER operation conditions of the H/He and D-T phases, the temperature distribution, flow rate, and pressure drop are investigated to meet the design requirements, and the temperature data are directly provided to a mechanical analysis.
doi_str_mv 10.1109/TPS.2016.2544918
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subjects Blanket
Coolants
design requirement
Electromagnetics
Fluid dynamics
Heating
helium-cooled ceramic reflector (HCCR) test blanket module (TBM) set
Hydraulics
ITER
Plasma temperature
RCC-MRx
TBM shield
Temperature distribution
Test methods
Thermal cycling
thermomechanical analysis
Thermomechanical processes
title Thermal-Hydraulic Analysis for Conceptual Design of Korean HCCR TBM Set
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