Scoping Study on In-Vessel LOCA of a Korean TBS in ITER

Korea has designed a helium cooled ceramic reflector (HCCR) based test blanket system (TBS) for an ITER. An in-vessel loss of coolant accident is one eight selected reference accidents in the Korean TBS. This accident is initiated by a single or multiple rupture of the test blanket module first wall...

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Bibliographic Details
Published in:IEEE transactions on plasma science 2014-03, Vol.42 (3), p.671-674
Main Authors: Jin, Hyung Gon, Lee, Dong Won, Lee, Eo Hwak, Kim, Suk Kwon, Yoon, Jae Sung, Ahn, Moo Yung, Cho, Seung Yon
Format: Article
Language:English
Subjects:
Accidents
Blanketing
Channels
Cooling
Forensic engineering
Fusion
Heating
Helium
In-vessel loss of coolant accident (LOCA)
ITER
LOCA
Modules
Plasma temperature
Pressure
Safety
safety analysis
scoping study
Simulation
Temperature
test blanket system (TBS)
Volume
Walls
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Summary:Korea has designed a helium cooled ceramic reflector (HCCR) based test blanket system (TBS) for an ITER. An in-vessel loss of coolant accident is one eight selected reference accidents in the Korean TBS. This accident is initiated by a single or multiple rupture of the test blanket module first wall cooling channels, causing a plasma disruption, and pressurization of the vacuum vessel (VV). In this type of accident, the governing parameters are various, for example, the operating pressure, gas temperature, TBS volume, VV volume, and mass flow rate. Thus, a scoping study is an essential strategy when attempting to determine the proper design specification for a Korean TBS. In this paper, given the preliminary accident analysis results for the current HCCR TBS, a parametric study was performed. For this transient simulation, the Korean nuclear fusion reactor safety analysis code (GAMMA-FR) was used.
ISSN:0093-3813
1939-9375
DOI:10.1109/TPS.2014.2303797