In-vessel design of ITER diagnostic neutron activation system

被引：21

作者：

Cheon, M. S. ^{[1
]}

Pak, S. ^{[1
]}

Lee, H. G. ^{[1
]}

Bertalot, L. ^{[2
]}

Walker, C. ^{[2
]}

机构：

[1] Natl Fus Res Inst, Taejon 305333, South Korea

[2] ITER Org, Cadarache Ctr, F-13108 St Paul Les Durance, France

来源：

REVIEW OF SCIENTIFIC INSTRUMENTS | 2008年 / 79卷 / 10期

关键词：

fusion reactor blankets; fusion reactor design; Monte Carlo methods; neutron activation analysis; plasma diagnostics; plasma simulation; Tokamak devices;

D O I：

10.1063/1.2990857

中图分类号：

TH7 [仪器、仪表];

学科分类号：

0804 ; 080401 ; 081102 ;

摘要：

A neutron activation system utilizing an encapsulated metal sample technique will be implemented to evaluate total fusion power from ITER plasma. The positions of seven irradiation ends for each poloidal section are determined to optimize the measurements from asymmetric, elongated plasma with minimum uncertainty. To determine the exact location of the irradiation end, some physical and technical aspects for each location are investigated. Monte Carlo neutronic calculations are performed to assess the physical characteristics and optimize the design of each irradiation end.

引用

页数：3

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