DocumentCode
1351643
Title
Operational Radioactivity Evaluation of ITER Diagnostic Neutron Activation System
Author
Cheon, M.S. ; Seon, C.R. ; Pak, S. ; Lee, H.G. ; Bertalot, L. ; Forrest, R.A.
Author_Institution
Nat. Fusion Res. Inst., Daejeon, South Korea
Volume
38
Issue
3
fYear
2010
fDate
3/1/2010 12:00:00 AM
Firstpage
274
Lastpage
277
Abstract
At the International Thermonuclear Experimental Reactor (ITER), a neutron activation system is foreseen to measure neutron fluence on the first wall and to evaluate total fusion power from ITER plasma. This system utilizes the method of counting gamma radiation from the metal sample irradiated by the neutron flux at the irradiation end located near the plasma. Evaluation of the operational radioactivity of the sample, which has been induced during ITER operation, is necessary in order to determine sample material, mass, and the appropriate irradiation time. Neutronic calculations are performed to evaluate operational activity of the sample. Activation of the sample is calculated according to the irradiation time for various sample materials such as Si, Al, Ti, Fe, Nb, and Cu and by assuming that the samples are irradiated at the midplane inboard region where the neutron flux is one of the strongest.
Keywords
Tokamak devices; neutron activation analysis; plasma diagnostics; plasma toroidal confinement; ITER plasma; International Thermonuclear Experimental Reactor; gamma radiation; irradiation time; neutron activation system; neutron fluence; neutron flux; neutronic calculations; operational radioactivity evaluation; total fusion power; Alite; ITER; MCNP; neutron activation; operational activity;
fLanguage
English
Journal_Title
Plasma Science, IEEE Transactions on
Publisher
ieee
ISSN
0093-3813
Type
jour
DOI
10.1109/TPS.2009.2036917
Filename
5350731
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