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Title: Effect of helium irradiation on deuterium permeation behavior in tungsten

Authors:
; ; ; ; ; ; ; ; ; ; ; ORCiD logo; ; ; ORCiD logo
Publication Date:
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24); USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1419349
Grant/Contract Number:
AC07-05ID14517; NA-0003525
Resource Type:
Journal Article: Publisher's Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 490; Journal Issue: C; Related Information: CHORUS Timestamp: 2018-02-01 23:11:05; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
Netherlands
Language:
English

Citation Formats

Uemura, Yuki, Sakurada, Shodai, Fujita, Hiroe, Azuma, Keisuke, Zhou, Quilai, Hatano, Yuji, Yoshida, Naoaki, Watanabe, Hideo, Oyaizu, Makoto, Isobe, Kanetsugu, Shimada, Masashi, Buchenauer, Dean, Kolasinski, Robert, Chikada, Takumi, and Oya, Yasuhisa. Effect of helium irradiation on deuterium permeation behavior in tungsten. Netherlands: N. p., 2017. Web. doi:10.1016/j.jnucmat.2017.04.041.
Uemura, Yuki, Sakurada, Shodai, Fujita, Hiroe, Azuma, Keisuke, Zhou, Quilai, Hatano, Yuji, Yoshida, Naoaki, Watanabe, Hideo, Oyaizu, Makoto, Isobe, Kanetsugu, Shimada, Masashi, Buchenauer, Dean, Kolasinski, Robert, Chikada, Takumi, & Oya, Yasuhisa. Effect of helium irradiation on deuterium permeation behavior in tungsten. Netherlands. doi:10.1016/j.jnucmat.2017.04.041.
Uemura, Yuki, Sakurada, Shodai, Fujita, Hiroe, Azuma, Keisuke, Zhou, Quilai, Hatano, Yuji, Yoshida, Naoaki, Watanabe, Hideo, Oyaizu, Makoto, Isobe, Kanetsugu, Shimada, Masashi, Buchenauer, Dean, Kolasinski, Robert, Chikada, Takumi, and Oya, Yasuhisa. Sat . "Effect of helium irradiation on deuterium permeation behavior in tungsten". Netherlands. doi:10.1016/j.jnucmat.2017.04.041.
@article{osti_1419349,
title = {Effect of helium irradiation on deuterium permeation behavior in tungsten},
author = {Uemura, Yuki and Sakurada, Shodai and Fujita, Hiroe and Azuma, Keisuke and Zhou, Quilai and Hatano, Yuji and Yoshida, Naoaki and Watanabe, Hideo and Oyaizu, Makoto and Isobe, Kanetsugu and Shimada, Masashi and Buchenauer, Dean and Kolasinski, Robert and Chikada, Takumi and Oya, Yasuhisa},
abstractNote = {},
doi = {10.1016/j.jnucmat.2017.04.041},
journal = {Journal of Nuclear Materials},
number = C,
volume = 490,
place = {Netherlands},
year = {Sat Jul 01 00:00:00 EDT 2017},
month = {Sat Jul 01 00:00:00 EDT 2017}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record at 10.1016/j.jnucmat.2017.04.041

Citation Metrics:
Cited by: 1work
Citation information provided by
Web of Science

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  • Permeability, diffusivity, and solubility of deuterium in the low-activation martensitic stainless steel EUROFER97 were derived from measurements of gas permeation in the transient and steady-state regimes at temperatures from 100 to 350 deg. C and at pressures from 2 x 10{sup 3} to 2 x 10{sup 5} Pa. The specimens were used in four conditions to investigate the effect of irradiation-induced defects: standard annealed condition, preirradiated with protons, implanted with helium, and implanted plus annealed to produce helium bubbles. In general, displacement defects as well as implanted helium tend to decrease permeation and diffusivity. Permeation and diffusion measurements were alsomore » performed under simultaneous irradiation, showing no net effect if the slight temperature increase due to irradiation is taken into account. Diffusion measurement of implanted hydrogen gave equal or slightly lower values than gas permeation, which is in qualitative agreement with results from preirradiated specimens. Trapping parameters are derived by a detailed comparison to a saturable-trap model. Results are compared to previous studies on 7%Cr F82H and 11%Cr MANET-II steels, and effects of compositional variations are indicated.« less
  • Here, to address the transport and trapping of hydrogen isotopes, several permeation experiments are being pursued at both Sandia National Laboratories (deuterium gas-driven permeation) and Idaho National Laboratories (tritium gas- and plasma-driven tritium permeation). These experiments are in part a collaboration between the US and Japan to study the performance of tungsten at divertor relevant temperatures (PHENIX). Here we report on the development of a high temperature (≤1150 °C) gas-driven permeation cell and initial measurements of deuterium permeation in several types of tungsten: high purity tungsten foil, ITER-grade tungsten (grains oriented through the membrane), and dispersoid-strengthened ultra-fine grain (UFG) tungstenmore » being developed in the US. Experiments were performed at 500–1000 °C and 0.1–1.0 atm D 2 pressure. Permeation through ITER-grade tungsten was similar to earlier W experiments by Frauenfelder (1968–69) and Zaharakov (1973). Data from the UFG alloy indicates marginally higher permeability (< 10×) at lower temperatures, but the permeability converges to that of the ITER tungsten at 1000 °C. The permeation cell uses only ceramic and graphite materials in the hot zone to reduce the possibility for oxidation of the sample membrane. Sealing pressure is applied externally, thereby allowing for elevation of the temperature for brittle membranes above the ductile-to-brittle transition temperature.« less
  • Abstract not provided.
  • Tungsten samples were irradiated by neutrons in the High Flux Isotope Reactor, Oak Ridge National Laboratory at reactor coolant temperatures of 50-70°C to low displacement damage of 0.025 and 0.3 dpa under the framework of the US-Japan TITAN program (2007-2013). After cooling down, the HFIR neutron-irradiated tungsten samples were exposed to deuterium plasmas in the Tritium Plasma Experiment, Idaho National Laboratory at 100, 200 and 500 °C twice at the ion fluence of 5×10²⁵ m⁻² to reach a total ion fluence of 1×10²⁶ m⁻² in order to investigate the near surface deuterium retention and saturation via nuclear reaction analysis. Finalmore » thermal desorption spectroscopy was performed to elucidate irradiation effect on total deuterium retention. Nuclear reaction analysis results showed that the maximum near surface (<5 µm depth) deuterium concentration increased from 0.5 at % D/W in 0.025 dpa samples to 0.8 at. % D/W in 0.3 dpa samples. The large discrepancy between the total retention via thermal desorption spectroscopy and the near surface retention via nuclear reaction analysis indicated the deuterium was migrated and trapped in bulk (at least 50 µm depth for 0.025 dpa and 35 µm depth for 0.025 dpa) at 500 °C case even in the relatively low ion fluence of 10²⁶ m⁻².« less