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

被引:3
|
作者
Youchison, Dennis L. [1 ]
Natoni, Greg [1 ]
Narula, Manmeet [2 ]
Ying, Alice [2 ]
机构
[1] Sandia Natl Labs, Albuquerque, NM 87185 USA
[2] Univ Calif Los Angeles, Los Angeles, CA 90095 USA
关键词
ITER; Plasma facing components; First wall; Shield; Computational fluid dynamics; Neutronics; Thermal stress; Finite element method;
D O I
10.1016/j.fusengdes.2008.08.013
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
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 hearing 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 hearing. 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. (C) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码:1025 / 1033
页数:9
相关论文
共 28 条
  • [21] Precise thermo-fluid dynamics analysis of corrugated wall distribution transformer cooled with mineral oil-based nanofluids: Experimental verification
    Abdali, Ali
    Abedi, Ali
    Mazlumi, Kazem
    Rabiee, Abbas
    Guerrero, Josep M.
    APPLIED THERMAL ENGINEERING, 2023, 221
  • [22] Thermo-Structural Analysis of CLAM steel and SS316L in the First Wall for ITER during Thermal Cycling
    Liu, Fubin
    Yao, Man
    Zhang, Pengbo
    Zhao, Jijun
    NEW MATERIALS AND ADVANCED MATERIALS, PTS 1 AND 2, 2011, 152-153 : 1716 - +
  • [23] Benchmark calculations for verification of thermo-fluid analysis codes using simplified model of the OECD/NEA MHTGR-350 core design
    Lee, Sung Nam
    Tak, Nam-il
    Lim, Hong-Sik
    Jo, Chang Keun
    Seker, Volkan
    Downar, Thomas J.
    ANNALS OF NUCLEAR ENERGY, 2020, 139
  • [24] Thermo-mechanical analysis of ITER first mirrors and its use for the ITER equatorial visible/infrared wide angle viewing system optical design
    Joanny, M.
    Salasca, S.
    Dapena, M.
    Cantone, B.
    Travere, J. M.
    Thellier, C.
    Ferme, J. J.
    Marot, L.
    Buravand, O.
    Perrollaz, G.
    Zeile, C.
    REVIEW OF SCIENTIFIC INSTRUMENTS, 2012, 83 (10):
  • [25] Thermo-mechanical stress analysis of the water cooled DEMO First Wall mock-up components
    Kamenicky, Robin
    Domalapally, Phani Kumar
    Arnoult, Xavier
    FUSION ENGINEERING AND DESIGN, 2018, 136 : 1618 - 1623
  • [26] First results and surface analysis strategy for plasma-facing components after JET operation with the ITER-like wall
    Likonen, J.
    Alves, E.
    Baron-Wiechec, A.
    Brezinsek, S.
    Coad, J. P.
    Hakola, A.
    Heinola, K.
    Koivuranta, S.
    Matthews, G. F.
    Petersson, P.
    Rubel, M.
    Stan-Sion, C.
    Widdowson, A.
    PHYSICA SCRIPTA, 2014, T159
  • [27] Thermo-fluid analysis on novel design of central impact-inlet double layered micro-channel heat sinks featured with bifurcation verified by experiments
    Cao, Xin
    Li, Peng
    Li, Yuying
    Bai, Lina
    Rosales-Vera, Marco
    Shen, Han
    INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, 2024, 156
  • [28] Thermohydraulic analysis of high-Prandtl-number fluid in complex duct simulating first wall in fusion reactor
    Satake, Masaaki
    Yuki, Kazuhisa
    Hashizume, Hidetoshi
    FUSION ENGINEERING AND DESIGN, 2010, 85 (02) : 234 - 242