Lay-out activities for the IFMIF high flux test module

被引：7

作者：

Heinzel, V ^{[1
]}

Fischer, U ^{[1
]}

Dolensky, B ^{[1
]}

Gordeev, S ^{[1
]}

Schleisiek, K ^{[1
]}

Simakov, SP ^{[1
]}

Slobodtchouk, V ^{[1
]}

Stratmanns, E ^{[1
]}

机构：

[1] Forschungszentrum Karlsruhe, Inst Reaktorsicherheit, D-76021 Karlsruhe, Germany

来源：

FUSION ENGINEERING AND DESIGN | 2002年 / 63-64卷

关键词：

IFMIF; high flux test module; helium cooling;

D O I：

10.1016/S0920-3796(02)00237-5

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：

Nuclear and thermal-hydraulic analydses have been performed with the objective to further optimise the high-fluxtest-module (HFTM) design. The nuclear analyses showed that the volume of 0.51 with a damage rate dpa/fpy > 20 can be achieved, if the HFTM has a contour like a semi ellipsoid. The thermal-hydraulic analyses focused on the experimental validation of the helium cooling concept. Integral heat transfer experiments revealed that the specimens can be kept at temperatures up to 600 degreesC. Dedicated experiments are being designed with the objective to provide data for the validation of the direct numeric FE simulation of the helium flow field, the heat transfer and the pressure losses. (C) 2002 Elsevier Science B.V. All rights reserved.

引用

页码：47 / 52

页数：6

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