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Thermal damage of tungsten-armored plasma-facing components under high heat flux loads
Fusion energy is expected as a promising candidate for alternative next generation energy. For fusion reactor, the plasma facing components (PFCs) are the most critical components to achieve this goal. PFCs will suffer severe thermal shock due to repective cyclic high heat flux (HHF) loads. This pap...
Autores principales: | , , , , , , |
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Formato: | Online Artículo Texto |
Lenguaje: | English |
Publicado: |
Nature Publishing Group UK
2020
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Materias: | |
Acceso en línea: | https://www.ncbi.nlm.nih.gov/pmc/articles/PMC6987102/ https://www.ncbi.nlm.nih.gov/pubmed/31992734 http://dx.doi.org/10.1038/s41598-020-57852-8 |
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author | Wang, Shuming Li, Jiangshan Wang, Ye Zhang, Xiaofang Wang, Ruiping Wang, Yanru Cao, Jian |
author_facet | Wang, Shuming Li, Jiangshan Wang, Ye Zhang, Xiaofang Wang, Ruiping Wang, Yanru Cao, Jian |
author_sort | Wang, Shuming |
collection | PubMed |
description | Fusion energy is expected as a promising candidate for alternative next generation energy. For fusion reactor, the plasma facing components (PFCs) are the most critical components to achieve this goal. PFCs will suffer severe thermal shock due to repective cyclic high heat flux (HHF) loads. This paper investigates the effects of thermal shock and damage behavior of tungsten armored PFCs under steady, transient and combined thermal loads. The distribution of stress field is analyzed, and crack initiation is predicted using the extended finite element method (XFEM). The unique features of thermal-mechanical behavior of tungsten armored PFCs under simulated service condition are discussed. The dominant factor of the cracking of the tungsten armor is the brittleness of tungsten below ductile-to-brittle transition temperature (DBTT). Under the steady loads, the cracking position is apt to near the interface of tungsten armor and the interlayer, and the threshold of cracking is between 14 MW/m(2) and 16 MW/m(2). With 6 MW/m(2) steady loads, applying 1 ms duration of transient load, the cracking threshold is between 0.2 GW/m(2) to 0.4 GW/m(2). The depth of cracking increases from 100 um to 500 um with the transient load increasing from 0.4 GW/m(2) to 1.0 GW/m(2). Researches are useful for the design and structural optimization of tungsten-armored PFCs, and the long-term stable operation of further reactor. |
format | Online Article Text |
id | pubmed-6987102 |
institution | National Center for Biotechnology Information |
language | English |
publishDate | 2020 |
publisher | Nature Publishing Group UK |
record_format | MEDLINE/PubMed |
spelling | pubmed-69871022020-01-31 Thermal damage of tungsten-armored plasma-facing components under high heat flux loads Wang, Shuming Li, Jiangshan Wang, Ye Zhang, Xiaofang Wang, Ruiping Wang, Yanru Cao, Jian Sci Rep Article Fusion energy is expected as a promising candidate for alternative next generation energy. For fusion reactor, the plasma facing components (PFCs) are the most critical components to achieve this goal. PFCs will suffer severe thermal shock due to repective cyclic high heat flux (HHF) loads. This paper investigates the effects of thermal shock and damage behavior of tungsten armored PFCs under steady, transient and combined thermal loads. The distribution of stress field is analyzed, and crack initiation is predicted using the extended finite element method (XFEM). The unique features of thermal-mechanical behavior of tungsten armored PFCs under simulated service condition are discussed. The dominant factor of the cracking of the tungsten armor is the brittleness of tungsten below ductile-to-brittle transition temperature (DBTT). Under the steady loads, the cracking position is apt to near the interface of tungsten armor and the interlayer, and the threshold of cracking is between 14 MW/m(2) and 16 MW/m(2). With 6 MW/m(2) steady loads, applying 1 ms duration of transient load, the cracking threshold is between 0.2 GW/m(2) to 0.4 GW/m(2). The depth of cracking increases from 100 um to 500 um with the transient load increasing from 0.4 GW/m(2) to 1.0 GW/m(2). Researches are useful for the design and structural optimization of tungsten-armored PFCs, and the long-term stable operation of further reactor. Nature Publishing Group UK 2020-01-28 /pmc/articles/PMC6987102/ /pubmed/31992734 http://dx.doi.org/10.1038/s41598-020-57852-8 Text en © The Author(s) 2020 Open Access This article is licensed under a Creative Commons Attribution 4.0 International License, which permits use, sharing, adaptation, distribution and reproduction in any medium or format, as long as you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons license, and indicate if changes were made. The images or other third party material in this article are included in the article’s Creative Commons license, unless indicated otherwise in a credit line to the material. If material is not included in the article’s Creative Commons license and your intended use is not permitted by statutory regulation or exceeds the permitted use, you will need to obtain permission directly from the copyright holder. To view a copy of this license, visit http://creativecommons.org/licenses/by/4.0/. |
spellingShingle | Article Wang, Shuming Li, Jiangshan Wang, Ye Zhang, Xiaofang Wang, Ruiping Wang, Yanru Cao, Jian Thermal damage of tungsten-armored plasma-facing components under high heat flux loads |
title | Thermal damage of tungsten-armored plasma-facing components under high heat flux loads |
title_full | Thermal damage of tungsten-armored plasma-facing components under high heat flux loads |
title_fullStr | Thermal damage of tungsten-armored plasma-facing components under high heat flux loads |
title_full_unstemmed | Thermal damage of tungsten-armored plasma-facing components under high heat flux loads |
title_short | Thermal damage of tungsten-armored plasma-facing components under high heat flux loads |
title_sort | thermal damage of tungsten-armored plasma-facing components under high heat flux loads |
topic | Article |
url | https://www.ncbi.nlm.nih.gov/pmc/articles/PMC6987102/ https://www.ncbi.nlm.nih.gov/pubmed/31992734 http://dx.doi.org/10.1038/s41598-020-57852-8 |
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