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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Main Authors: 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
Format: Article
Language:English
Published: Elsevier 2017-08-01
Series:Nuclear Materials and Energy
Online Access:http://www.sciencedirect.com/science/article/pii/S2352179116301582
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spelling 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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