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.2008.08.013Additional 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)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40087243
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOUNDARY CONDITIONS; COMPUTERIZED SIMULATION; DESIGN; FINITE ELEMENT METHOD; FIRST WALL; FLUID MECHANICS; GEOMETRY; HEAT FLUX; HEAT TRANSFER; ITER TOKAMAK; NEUTRONS; PRESSURE DROP; RADIATION HEATING; SHIELDS; STRESS ANALYSIS; THERMAL STRESSES
- Descriptors DEC
- BARYONS; CALCULATION METHODS; CLOSED PLASMA DEVICES; ELEMENTARY PARTICLES; ENERGY TRANSFER; FERMIONS; HADRONS; HEATING; MATHEMATICAL SOLUTIONS; MATHEMATICS; MECHANICS; NUCLEONS; NUMERICAL SOLUTION; SIMULATION; STRESSES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.