Irradiation effects of hydrogen and helium plasma on different grade tungsten materials
Fine-grain tungsten alloys could be one of the solutions for the plasma facing materials of future DEMO reactors. In order to evaluate the service performances of the newly developed W alloys under edge plasma irradiation and the synergetic effect of fusion plasma together with high heat flux, both...
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doaj-09eaf972ccef422093975cec3cc9ea662020-11-25T00:09:56ZengElsevierNuclear Materials and Energy2352-17912017-08-011213141318Irradiation effects of hydrogen and helium plasma on different grade tungsten materialsX. Liu0Y.Y. Lian1H. Greuner2B. Boeswirth3Y.Z. Jin4F. Feng5J.B. Wang6L. Chen7J.P. Song8Y. Yu9T. Zhang10C.S. Liu11J. Tan12D.P. Liu13X.R. Duan14Southwestern Institute of Physics, P.O. Box 432, Chengdu 610041, Sichuan, China; Corresponding author.Southwestern Institute of Physics, P.O. Box 432, Chengdu 610041, Sichuan, ChinaMax Planck Institute for Plasma Physics, D-85748 Garching, GermanyMax Planck Institute for Plasma Physics, D-85748 Garching, GermanySouthwestern Institute of Physics, P.O. Box 432, Chengdu 610041, Sichuan, ChinaSouthwestern Institute of Physics, P.O. Box 432, Chengdu 610041, Sichuan, ChinaSouthwestern Institute of Physics, P.O. Box 432, Chengdu 610041, Sichuan, ChinaSouthwestern Institute of Physics, P.O. Box 432, Chengdu 610041, Sichuan, ChinaXiamen Tungsten & Molybdenum Industry Co., Ltd. Xiamen, ChinaXiamen Tungsten & Molybdenum Industry Co., Ltd. Xiamen, ChinaInstitute of Solid State Physics, Chinese Academy of Science, Hefei, Anhui, ChinaInstitute of Solid State Physics, Chinese Academy of Science, Hefei, Anhui, ChinaInstitute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, Sichuan, ChinaDalian Nationality University, Dalian 116600, Liaoning, ChinaSouthwestern Institute of Physics, P.O. Box 432, Chengdu 610041, Sichuan, ChinaFine-grain tungsten alloys could be one of the solutions for the plasma facing materials of future DEMO reactors. In order to evaluate the service performances of the newly developed W alloys under edge plasma irradiation and the synergetic effect of fusion plasma together with high heat flux, both low energy He ions and high energy H, H/He mixed neutral beam irradiation on W-ZrC, W-K, W-Y2O3, W-La2O3 and CVD-W coating were performed respectively at a liner plasma facility (Dalian Nationality University, China) and the neutral beam facility GLADIS (IPP, Germany). Surface damages were characterized, and the crack formation and extension behaviors under ELM-like transient loading after H and H/He mixed beam irradiation were also investigated in the 60kW EMS-60 facility (Electron beam Materials testing Scenario) at SWIP (Southwestern Institute of Physics, China). The experimental results indicated that surface damages induced by low or high energy H/He ion/neutral beam didn't closely correlate with the type of tungsten materials. However, H/He (6at% He concentration) neutral beam induced more significant surface damages of the tested W materials than only H neutral beam irradiation under the similar irradiation conditions. Similarly, the mixed H/He pre-exposure remarkably reduced the critical power of crack initiation compared with the un-irradiated samples under 100 repetitive loads of 1ms pulse, while no significant degeneration for the case of only H beam irradiation was observed. Keywords: CVD-W coating, Dispersion strengthened W alloys, Divertor, H/He irradiation, Surface damages, Crack initiationhttp://www.sciencedirect.com/science/article/pii/S2352179116301582 |
collection |
DOAJ |
language |
English |
format |
Article |
sources |
DOAJ |
author |
X. Liu Y.Y. Lian H. Greuner B. Boeswirth Y.Z. Jin F. Feng J.B. Wang L. Chen J.P. Song Y. Yu T. Zhang C.S. Liu J. Tan D.P. Liu X.R. Duan |
spellingShingle |
X. Liu Y.Y. Lian H. Greuner B. Boeswirth Y.Z. Jin F. Feng J.B. Wang L. Chen J.P. Song Y. Yu T. Zhang C.S. Liu J. Tan D.P. Liu X.R. Duan Irradiation effects of hydrogen and helium plasma on different grade tungsten materials Nuclear Materials and Energy |
author_facet |
X. Liu Y.Y. Lian H. Greuner B. Boeswirth Y.Z. Jin F. Feng J.B. Wang L. Chen J.P. Song Y. Yu T. Zhang C.S. Liu J. Tan D.P. Liu X.R. Duan |
author_sort |
X. Liu |
title |
Irradiation effects of hydrogen and helium plasma on different grade tungsten materials |
title_short |
Irradiation effects of hydrogen and helium plasma on different grade tungsten materials |
title_full |
Irradiation effects of hydrogen and helium plasma on different grade tungsten materials |
title_fullStr |
Irradiation effects of hydrogen and helium plasma on different grade tungsten materials |
title_full_unstemmed |
Irradiation effects of hydrogen and helium plasma on different grade tungsten materials |
title_sort |
irradiation effects of hydrogen and helium plasma on different grade tungsten materials |
publisher |
Elsevier |
series |
Nuclear Materials and Energy |
issn |
2352-1791 |
publishDate |
2017-08-01 |
description |
Fine-grain tungsten alloys could be one of the solutions for the plasma facing materials of future DEMO reactors. In order to evaluate the service performances of the newly developed W alloys under edge plasma irradiation and the synergetic effect of fusion plasma together with high heat flux, both low energy He ions and high energy H, H/He mixed neutral beam irradiation on W-ZrC, W-K, W-Y2O3, W-La2O3 and CVD-W coating were performed respectively at a liner plasma facility (Dalian Nationality University, China) and the neutral beam facility GLADIS (IPP, Germany). Surface damages were characterized, and the crack formation and extension behaviors under ELM-like transient loading after H and H/He mixed beam irradiation were also investigated in the 60kW EMS-60 facility (Electron beam Materials testing Scenario) at SWIP (Southwestern Institute of Physics, China). The experimental results indicated that surface damages induced by low or high energy H/He ion/neutral beam didn't closely correlate with the type of tungsten materials. However, H/He (6at% He concentration) neutral beam induced more significant surface damages of the tested W materials than only H neutral beam irradiation under the similar irradiation conditions. Similarly, the mixed H/He pre-exposure remarkably reduced the critical power of crack initiation compared with the un-irradiated samples under 100 repetitive loads of 1ms pulse, while no significant degeneration for the case of only H beam irradiation was observed. Keywords: CVD-W coating, Dispersion strengthened W alloys, Divertor, H/He irradiation, Surface damages, Crack initiation |
url |
http://www.sciencedirect.com/science/article/pii/S2352179116301582 |
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