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Radiation Protection Dosimetry 2005 116(1-4):24-27; doi:10.1093/rpd/nci242
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© The Author 2005. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

Radioactivity evaluation for the KSTAR tokamak

Hyunduk Kim1, Hee-Seock Lee1,*, Sukmo Hong1, Minho Kim1, Chinwha Chung1 and Changsuk Kim2

1 Pohang Accelerator Laboratory, POSTECH, Pohang 790-784, Korea
2 Korea Basic Science Institute, Yusung-gu, Daejeon 305-333, Korea

* Corresponding author: lee{at}postech.ac.kr

The deuterium–deuterium (D–D) reaction in the KSTAR (Korea Superconducting Tokamak Advanced Research) tokamak generates neutrons with a peak yield of 2.5x1016 s–1 through a pulse operation of 300 s. Since the structure material of the tokamak is irradiated with neutrons, this environment will restrict work around and inside the tokamak from a radiation protection physics point of view after shutdown. Identification of neutron-produced radionuclides and evaluation of absorbed dose in the structure material are needed to develop a guiding principle for radiation protection. The activation level was evaluated by MCNP4C2 and an inventory code, FISPACT. The absorbed dose in the working area decreased by 4.26x10–4 mrem h–1 in the inner vessel 1.5 d after shutdown. Furthermore, tritium strongly contributes to the contamination in the graphite tile. The amount of tritium produced by neutrons was 3.03 x 106 Bq kg–1 in the carbon graphite of a plasma-facing wall.


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