Published November 1, 2016 | Version v1
Journal article

Assessment of the W7-X high heat flux divertor with thermo-mechanical analysis

  • 1. Institute of Plasma Physics, Chinese Academy of Sciences, Shushanhu Road 350, 230031 Hefei, Anhui (China)
  • 2. School of Nuclear Science and Technology, University of Science and Technology of China, Jinzhai Road 96, 230026 Hefei,Anhui (China)
  • 3. Max Planck Institute for Plasma Physics, Wendelsteinstr. 1, 17491 Greifswald (Germany)
  • 4. Max Planck Institute for Plasma Physics, Boltzmannstr. 2, 85748 Garching (Germany)

Description

Highlights: • Thermo-mechanical analysis of HHF divertor module, TM2H. • Temperature of all parts is acceptable for long pulse operation. • Stress in different parts is mainly caused by different load. • Radial displacement need to be improved based on FE calculations. - Abstract: The Wendelstein 7-X is an experimental device designed with a stellarator magnetic confinement for stationary plasma operation (up to 30 min). At the first stage, it is scheduled to start with an inertially cooled test divertor unit and a shorter plasma pulse operation up to 10 s. After the completion of this stage, a water-cooled high heat flux (HHF) divertor will be installed for the steady-state operation phase. The divertor consists of individual target modules, which are sets of target elements armored with CFC tiles supported by a stainless steel structure and fed in parallel with manifolds. Detailed thermo-mechanical analysis of the target modules using the finite element method has been performed to validate and/or improve the elected design of the HHF divertor under operation. Different operating conditions have been studied and the effect of the variation of the convective heat flux pattern with localized heating loads as high as 10 MW/m2 onto the target elements has been computed. The analysis of the thermal response, stress distribution and deformation allowed a better understanding of the behavior of the divertor modules under operation and confirmed the suitability of the design.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2016.02.045

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2016.02.045;
PII
S0920-3796(16)30127-2;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
109-111
Journal Issue
Part A
Journal Page Range
p. 565-568
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
12. international symposium on fusion nuclear technology
Acronym
ISFNT-12
Dates
14-18 Sep 2015
Place
Jeju Island (Korea, Republic of)

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.