Operational Radioactivity Evaluation of ITER Diagnostic Neutron Activation System

被引:9
作者
Cheon, M. S. [1 ]
Seon, C. R. [1 ]
Pak, S. [1 ]
Lee, H. G. [1 ]
Bertalot, L. [2 ]
Forrest, R. A. [3 ]
机构
[1] Natl Fusion Res Inst, Taejon 305333, South Korea
[2] Cadarache Ctr, ITER Org, F-13108 St Paul Les Durance, France
[3] UKAEA Euratom Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
基金
英国工程与自然科学研究理事会;
关键词
Alite; ITER; MCNP; neutron activation; operational activity; YIELDS; DT;
D O I
10.1109/TPS.2009.2036917
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
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.
引用
收藏
页码:274 / 277
页数:4
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