Published December 2008 | Version v1
Journal article

Computational thermo-fluid exploratory design analysis for complex ITER first wall/shield components

  • 1. Sandia National Laboratories, Albuquerque, NM 87185 (United States)
  • 2. University of California, Los Angeles, CA 90095 (United States)

Description

Engineers in the ITER US Party Team used several computational fluid dynamics codes to evaluate design concepts for the ITER first wall panels and the neutron shield modules. The CFdesign code enabled them to perform design studies of modules 7 and 13 very efficiently. CFdesign provides a direct interface to the CAD program, CATIA v5. The geometry input and meshing are greatly simplified. CFdesign is a finite element code, rather than a finite volume code. Flow experiments and finite volume calculations from SC-Tetra, Fluent and CFD2000 verified the CFdesign results. Several new enhancements allow CFdesign to export temperatures, pressures and convective heat transfer coefficients to other finite element models for further analysis. For example, these loads and boundary conditions directly feed into codes such as ABAQUS to perform stress analysis. In this article, we review the use of 2- and 4-mm flow driver gaps in the shield modules and the use of 1-mm gaps along the tee-vane in the front water header to obtain a good flow distribution in both the first wall and shield modules for 7 and 13. Plasma heat flux as well as neutron heating derived from MCNP calculations is included in the first wall and shield module analyses. We reveal the non-uniformity of the convective heat transfer coefficient inside complex 3D geometries exposed to a one-sided heat flux and non-uniform volumetric heating. Most models consisted of 3-4 million tetrahedron elements. We obtained temperature and velocity distributions, as well as pressure drop information, for models of nearly exact geometry compared to the CATIA fabrication models. We also describe the coupling to thermal stress analysis in ABAQUS. The results presented provide confidence that the preliminary design of these plasma facing components will meet ITER requirements

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2008.08.013

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2008.08.013;
PII
S0920-3796(08)00256-1;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
83
Journal Issue
7-9
Journal Page Range
p. 1025-1033
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
8. international symposium of fusion nuclear technology
Acronym
ISFNT-8 SI
Dates
30 Sep - 5 Oct 2007
Place
Heidelberg (Germany)

Optional Information

Copyright
Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.