NDLI: Aggravated blistering and increased deuterium retention in iron-damaged tungsten after exposure to deuterium plasma with various surface temperatures

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Aggravated blistering and increased deuterium retention in iron-damaged tungsten after exposure to deuterium plasma with various surface temperatures

Content Provider	Scilit
Author	Zhu, Xiu-Li Zhang, Ying Kreter, Arkadi Shi, Li-Qun Yuan, Yue Cheng, Long Linsmeier, Christian Lu, Guang-Hong
Copyright Year	2018
Description	Journal: Nuclear Fusion Effects of iron ion pre-irradiation with energy of 1 MeV on deuterium retention and blistering in tungsten has been investigated after exposure to low-energy (40 eV) and high flux (~1022 D/m2s) deuterium plasma under high fluence of 1×1026 D/m2 with various surface temperatures (450 K, 550 K and 750 K). The undamaged and pre-damaged tungsten show a similar temperature dependence of deuterium-induced blistering, as well as deuterium retention in the near surface (within 300 nm). Deuterium concentration in the near surface decreases with increasing the surface temperature in deuterium plasma exposure. For both cases, the most serious blistering is present with the surface temperature of 550 K. Due to the creation of pre-damage blisters becomes much larger and the near-surface deuterium concentration becomes higher. Analysis of blistering-related cavities in the pre-damaged and undamaged tungsten indicates that in pre-damaged tungsten deuterium aggregates in the place with a much larger depth. Based on the comparison of the pre-damage induced increment of deuterium retention within the near surface region (damage layer) and in the bulk, it reveals that the pre-damage enhances deuterium retention in the bulk more strongly than that in the near-surface region, suggesting that the deuterium flux diffusing into the bulk of pre-damaged tungsten is largely improved.
Related Links	http://iopscience.iop.org/article/10.1088/1741-4326/aad1a0/pdf
ISSN	00295515
e-ISSN	17414326
DOI	10.1088/1741-4326/aad1a0
Journal	Nuclear Fusion
Issue Number	10
Volume Number	58
Language	English
Publisher	IOP Publishing
Publisher Date	2018-07-06
Access Restriction	Open
Subject Keyword	Journal: Nuclear Fusion Nuclear Energy and Engineering Deuterium Retention Damaged Tungsten Pre Damaged
Content Type	Text
Resource Type	Article
Subject	Nuclear and High Energy Physics Condensed Matter Physics

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