Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions

被引:133
作者
Marian, Jaime [1 ]
Becquart, Charlotte S. [2 ]
Domain, Christophe [3 ]
Dudarev, Sergei L. [4 ]
Gilbert, Mark R. [4 ]
Kurtz, Richard J. [5 ]
Mason, Daniel R. [4 ]
Nordlund, Kai [6 ]
Sand, Andrea E. [6 ]
Snead, Lance L. [7 ]
Suzudo, Tomoaki [8 ]
Wirth, Brian D. [9 ]
机构
[1] Univ Calif Los Angeles, Los Angeles, CA 90095 USA
[2] Univ Lille, UMET, ENSCL, UMR 8207, F-59655 Villeneuve Dascq, France
[3] EDF R&D, Dept MMC, F-77250 Les Renardieres, Moret Sur Loing, France
[4] Culham Sci Ctr, Culham Ctr Fus Energy, Abingdon OX14 3DB, Oxon, England
[5] Pacific Northwest Natl Lab, Richland, WA USA
[6] Univ Helsinki, Dept Phys, POB 43, FI-00014 Helsinki, Finland
[7] MIT, 77 Massachusetts Ave, Cambridge, MA 02139 USA
[8] Japan Atom Energy Agcy, Tokai, Ibaraki, Japan
[9] Univ Tennessee, Knoxville, TN USA
关键词
modeling and simulation; plasma-facing materials; tungsten; neutron irradiation; fusion materials; KINETIC MONTE-CARLO; MOLECULAR-DYNAMICS SIMULATIONS; AB-INITIO CALCULATIONS; RADIATION-DAMAGE; DEFECT PRODUCTION; GRAIN-BOUNDARY; INTERATOMIC POTENTIALS; MICROSTRUCTURAL DEVELOPMENT; DISPLACEMENT CASCADES; IRRADIATED TUNGSTEN;
D O I
10.1088/1741-4326/aa5e8d
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
Under the anticipated operating conditions for demonstration magnetic fusion reactors beyond ITER, structural and plasma-facing materials will be exposed to unprecedented conditions of irradiation, heat flux, and temperature. While such extreme environments remain inaccessible experimentally, computational modeling and simulation can provide qualitative and quantitative insights into materials response and complement the available experimental measurements with carefully validated predictions. For plasma-facing components such as the first wall and the divertor, tungsten (W) has been selected as the leading candidate material due to its superior high-temperature and irradiation properties, as well as for its low retention of implanted tritium. In this paper we provide a review of recent efforts in computational modeling of W both as a plasma-facing material exposed to He deposition as well as a bulk material subjected to fast neutron irradiation. We use a multiscale modeling approach-commonly used as the materials modeling paradigm-to define the outline of the paper and highlight recent advances using several classes of techniques and their interconnection. We highlight several of the most salient findings obtained via computational modeling and point out a number of remaining challenges and future research directions.
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页数:26
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