Perspectives on multiscale modelling and experiments to accelerate materials development for fusion

JOURNAL OF NUCLEAR MATERIALS

卷:554

Review

Gilbert, M. R.⁴  Arakawa, K.¹  Bergstrom, Z.²  Caturla, M. J.³  Dudarev, S. L.⁴  Gao, F.⁵  Goryaeva, A. M.⁶  Hu, S. Y.⁷  Hu, X.⁸  Kurtz, R. J.⁷  Litnovsky, A.^9,10  Marian, J.¹¹  Marinica, M-C⁶  Martinez, E.^12,13  Marquis, E. A.¹⁴  Mason, D. R.⁴  Nguyen, B. N.⁷  Olsson, P.¹⁵  Osetskiy, Y.⁸  Senor, D.⁷  Setyawan, W.⁷  Short, M. P.¹⁶  Suzudo, T.¹⁷  Trelewicz, J. R.¹⁸  Tsuru, T.¹⁷  Was, G. S.⁵  Wirth, B. D.²  Yang, L.²  Zhang, Y.⁸  Zinkle, S. J.² 

[1] Shimane Univ, Next Generat TATARA Cocreat Ctr, Matsue, Shimane, Japan

[2] Univ Tennessee, Knoxville, TN USA

[3] Univ Alicante, Fac Ciencias, Dept Fsica Aplicada, Fase 2, Alicante, Spain

[4] Culham Sci Ctr, Culham Ctr Fus Energy, United Kingdom Atom Energy Author, Abingdon 0X14 3DB, Oxon, England

[5] Univ Michigan, Dept Nucl Engn & Radiol Sci, Ann Arbor, MI 48109 USA

[6] Univ Paris Saclay, Serv Rech Met Phys, CEA, F-91191 Gif Sur Yvette, France

[7] Pacific Northwest Natl Lab, Richland, WA 99352 USA

[8] Oak Ridge Natl Lab, Mat Sci & Technol Div, POB 2009, Oak Ridge, TN 37831 USA

[9] Forschungszentrum Julich, Inst Energie AndKlimaforsch, D-52425 Julich, Germany

[10] Natl Nucl Res Univ MEPhI, Kashirskoe Sh 31, Moscow 115409, Russia

[11] Univ Calif Los Angeles, Dept Mat Sci & Engn, Los Angeles, CA 90024 USA

[12] Clemson Univ, Dept Mech Engn, Clemson, SC 29623 USA

[13] Clemson Univ, Dept Mat Sci & Engn, Clemson, SC 29623 USA

[14] Univ Michigan, Dept Mat Sci & Engn, Ann Arbor, MI 48104 USA

[15] KTH Royal Inst Technol, Nucl Engn, SE-10691 Stockholm, Sweden

[16] MIT, Dept Nucl Sci & Engn, 77 Massachusetts Ave, Cambridge, MA 02139 USA

[17] Japan Atom Energy Agcy, Tokai, Ibaraki, Japan

[18] SUNY Stony Brook, Dept Mat Sci & Chem Engn, Stony Brook, NY 11794 USA

关键词: Multiscale modelling;    Fusion materials;    Radiation damage;    Hydrogen and helium;    Defect evolution;    Experimental characterisation;   

DOI  :  10.1016/j.jnucmat.2021.153113

来源: Elsevier

【 摘 要 】

Prediction of material performance in fusion reactor environments relies on computational modelling, and will continue to do so until the first generation of fusion power plants come on line and allow long-term behaviour to be observed. In the meantime, the modelling is supported by experiments that attempt to replicate some aspects of the eventual operational conditions. In 2019, a group of leading experts met under the umbrella of the IEA to discuss the current position and ongoing challenges in modelling of fusion materials and how advanced experimental characterisation is aiding model improvement. This review draws from the discussions held during that workshop. Topics covering modelling of irradiation-induced defect production and fundamental properties, gas behaviour, clustering and segregation, defect evolution and interactions are discussed, as well as new and novel multiscale simulation approaches, and the latest effort s to link modelling to experiments through advanced observation and characterisation techniques. Crown Copyright (c) 2021 Published by Elsevier B.V. This is an open access article under the Open Government License (OGL) ( http://www.nationalarchives.gov.uk/doc/open-government-licence/version/3/ )

【 授权许可】

Free