Status of the IDTF high-heat-flux test facility

被引：34

作者：

Kuznetsov, V. ^{[1
]}

Gorbenko, A. ^{[1
]}

Davydov, V. ^{[1
]}

Kokoulin, A. ^{[1
]}

Komarov, A. ^{[1
]}

Mazul, I. ^{[1
]}

Mudyugin, B. ^{[1
]}

Ovchinnikov, I. ^{[1
]}

Stepanov, N. ^{[1
]}

Rulev, R. ^{[1
]}

Volodin, A. ^{[1
]}

机构：

[1] JSC NIIEFA, St Petersburg 196641, Russia

来源：

FUSION ENGINEERING AND DESIGN | 2014年 / 89卷 / 7-8期

关键词：

e-Beam; HHF tests; Divertor;

D O I：

10.1016/j.fusengdes.2014.04.064

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The ITER Divertor Test Facility (IDTF) was designed for the high heat flux tests of outer vertical targets, inner vertical targets and domes of the ITER divertor. This facility was created in the Efremov Institute under the Procurement Arrangement 1.7.P2D.RF (high heat flux tests of the plasma facing units of the ITER divertor). The heat flux is generated by an electron-beam system (EBS), 800 kW power and 60 kV maximum accelerating voltage. The component to be tested is mounted on a manipulator in the vacuum chamber capable of testing objects up to 2.5 m long and 1.5 m wide. The pressure in the vacuum chamber is about 3*10(-3) Pa. The parameters of the cooling system and the water quality (deionized water) are similar to the cooling conditions of the ITER divertor. The integrated control system regulates all IDTF subsystems and data acquisition from all diagnostic devices, such as pyrometers, IR-cameras, video cameras, flow, pressure and temperature sensors. Started in 2008, the IDTF was commissioned in 2012 with the testing the outer vertical full-scale prototypes and the completion of the PA 1.7.P2D.RF task. This paper details the main characteristics of the IDTF. (c) 2014 Elsevier B.V. All rights reserved.

引用

页码：955 / 959

页数：5

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