Flow and heat transfer characteristics of helium cooled IFMIF High Flux Test Module

被引：5
|
作者：
Chen, Yuming [1 ]
Arbeiter, Frederik [1 ]
机构：
[1] Karlsruhe Inst Technol, Inst Neutron Phys & Reactor Technol, D-76344 Eggenstein Leopoldshafen, Germany
来源：
FUSION ENGINEERING AND DESIGN | 2012年 / 87卷 / 5-6期
关键词：
IFMIF; HFTM; Thermohydraulic; Conjugate heat transfer; Numerical simulation;
D O I：
10.1016/j.fusengdes.2012.01.011
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 International Fusion Materials Irradiation Facility (IFMIF) is designated to generate a materials irradiation database for the future fusion reactors. The High Flux Test Module (HFTM) is located behind the lithium target where a structural damage rate of more than 20 dpa/fpy in steel specimen will be achieved in a volume of about 0.51. This paper concerns the thermo-hydraulic simulations of the HFTM with Ansys-CFX. The simulation domain consists of the whole HFTM with short fluid inlet and outlet sections. The turbulence models were assessed by comparing the simulations with in-house annular channel experiments. The flow distributions and heat transfer characteristics among various HETM sub-channels are the main focuses of this study. (C) 2012 Elsevier B.V. All rights reserved.
引用
收藏
页码：530 / 534
页数：5
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