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Behaviors of full compositional W/Cu functionally gradient materials exposed to the edge plasma of HT-7 tokamak
To investigate the behaviors of graded structure materials under plasma loading, six-layered W/Cu functionally gradient materials (FGMs) with full compositional distributions (from 0% to 100%) were successfully fabricated by resistance sintering under ultra-high pressure (RSUHP) method and were expo...
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Published in: | Journal of nuclear materials 2013-04, Vol.435 (1-3), p.107-111 |
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container_end_page | 111 |
container_issue | 1-3 |
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container_title | Journal of nuclear materials |
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creator | Zhu, D.H. Chen, J.L. Zhou, Z.J. Yan, R. Ding, R. |
description | To investigate the behaviors of graded structure materials under plasma loading, six-layered W/Cu functionally gradient materials (FGMs) with full compositional distributions (from 0% to 100%) were successfully fabricated by resistance sintering under ultra-high pressure (RSUHP) method and were exposed to the edge plasma of the HT-7 tokamak. After about 210 shots plasma loading with an estimated power density in the range of 2–7MW/m2, there is no detaching found at the graded interface corners where the thermal stress concentration is expected and the fatigue failures often occur initially, however, the brittle W layer develops the macroscopic cracks which can extend deeply into the interface and results in the interface failure or even the exfoliated W layer. To avoid these destructions for W/Cu FGMs during wall application, it is necessary to ameliorate the W layer by optimizing the initial powders and sintering parameters. |
doi_str_mv | 10.1016/j.jnucmat.2012.12.044 |
format | article |
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After about 210 shots plasma loading with an estimated power density in the range of 2–7MW/m2, there is no detaching found at the graded interface corners where the thermal stress concentration is expected and the fatigue failures often occur initially, however, the brittle W layer develops the macroscopic cracks which can extend deeply into the interface and results in the interface failure or even the exfoliated W layer. To avoid these destructions for W/Cu FGMs during wall application, it is necessary to ameliorate the W layer by optimizing the initial powders and sintering parameters.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2012.12.044</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; Copper ; Cracks ; Density ; Energy ; Energy. 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After about 210 shots plasma loading with an estimated power density in the range of 2–7MW/m2, there is no detaching found at the graded interface corners where the thermal stress concentration is expected and the fatigue failures often occur initially, however, the brittle W layer develops the macroscopic cracks which can extend deeply into the interface and results in the interface failure or even the exfoliated W layer. To avoid these destructions for W/Cu FGMs during wall application, it is necessary to ameliorate the W layer by optimizing the initial powders and sintering parameters.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2012.12.044</doi><tpages>5</tpages></addata></record> |
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subjects | Applied sciences Controled nuclear fusion plants Copper Cracks Density Energy Energy. Thermal use of fuels Exact sciences and technology Exposure Fatigue failure Fission nuclear power plants Fuels Functionally gradient materials Installations for energy generation and conversion: thermal and electrical energy Nuclear fuels Stress concentration Tokamak devices |
title | Behaviors of full compositional W/Cu functionally gradient materials exposed to the edge plasma of HT-7 tokamak |
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