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Radioactivity evaluation for the KSTAR tokamak.

Authors :
Kim H
Lee HS
Hong S
Kim M
Chung C
Kim C
Source :
Radiation protection dosimetry [Radiat Prot Dosimetry] 2005; Vol. 116 (1-4 Pt 2), pp. 24-7.
Publication Year :
2005

Abstract

The deuterium-deuterium (D-D) reaction in the KSTAR (Korea Superconducting Tokamak Advanced Research) tokamak generates neutrons with a peak yield of 2.5 x 10(16) 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 4.26 x 10(-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 10(6) Bq kg(-1) in the carbon graphite of a plasma-facing wall.

Details

Language :
English
ISSN :
0144-8420
Volume :
116
Issue :
1-4 Pt 2
Database :
MEDLINE
Journal :
Radiation protection dosimetry
Publication Type :
Academic Journal
Accession number :
16604589
Full Text :
https://doi.org/10.1093/rpd/nci242