Abstract
KSTAR is a medium size fully superconducting tokamak. The deuterium-deuterium (D-D) reaction in the KSTAR tokamak generates neutrons with a peak yield of 3.5x1016 per second through a pulse operation of 100 seconds. The effect of neutron generation from full D-D high power KSTAR operation mode to the machine, such as activation, shutdown dose rate, and nuclear heating, are estimated for an assurance of safety during operation, maintenance, and machine upgrade. The nuclear heating of the in-vessel components, and neutron activation of the surrounding materials have been investigated. The dose rates during operation and after shutdown of KSTAR have been calculated by a 3D CAD model of KSTAR with the Monte Carlo code MCNP5 (neutron flux and decay photon), the inventory code FISPACT (activation and decay photon) and the FENDL 2.1 nuclear data library.
Highlights
KSTAR started its operation from 2008 by creating first plasma and successfully completed its 1st phase of operation for 5 years by achieving H-mode plasma. It is in its 2nd phase operation aiming heating power of 28MW and developing Advanced Tokamak (AT) operation technology
At its 3rd operation stage from year 2018 with heating power of 28MW KSTAR is aiming for stable AT operation mode with full D-D plasma
At the last operation stage KSTAR would be utilized as a DEMO relevant facility
Summary
KSTAR started its operation from 2008 by creating first plasma and successfully completed its 1st phase of operation for 5 years by achieving H-mode plasma. It is in its 2nd phase operation aiming heating power of 28MW and developing Advanced Tokamak (AT) operation technology. Since the tritium population is quite small compared to deuterium ions, the 14.1MeV neutron production are about 2% of the 2.45MeV neutrons When these fusion reaction generated neutrons are irradiated onto the internal structure of tokamak all of the components are activated and give a serious radiation safety cause to human beings and delicate internal components. This research reduce the calculation error by implementing a more refined and accurate structural data with updated tokamak structure material information
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