Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron

Kobayashi, Makoto; Shimada, Masashi; Taylor, Chase N.; Buchenauer, Dean; Kolasinski, Robert; Koyanagi, Takaaki; Nobuta, Yuji; Hatano, Yuji; Oya, Yasuhisa

doi:10.1016/j.fusengdes.2019.03.003

Title: Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron

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Abstract

Tungsten (W) samples were damaged by neutron and 6.4 MeV Fe-ion irradiation above 1000 K simulating the divertor operation temperature. Deuterium (D) retention properties were examined by decorating the damaged W with D and subsequent thermal desorption spectroscopy (TDS) measurements. Vacancy clusters were the major D trapping site in the W irradiated with Fe-ion at 873 K, although D retention by vacancy clusters decreased in the W irradiated with Fe-ion at 1173 K due to dynamic annealing. The D de-trapping activation energy from vacancy clusters was found to be 1.85 eV. D retention in neutron damage W was larger than that damaged by Fe-ion due to the uniform distribution of irradiation defects. The D desorption behaviors from neutron damaged W was simulated well by assuming the D de-trapping activation energy to be 1.52 eV.

Authors:

^[1];

^[2];

^[2]; Buchenauer, Dean ^[3]; Kolasinski, Robert ^[3]; Koyanagi, Takaaki ^[4]; Nobuta, Yuji ^[5];

^[6];

^[7]

National Inst. for Fusion Science, National Inst. of Natural Sciences (Japan)
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sandia National Lab. (SNL-CA), Livermore, CA (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Hokkaido Univ., Sapporo (Japan)
Univ. of Toyama, Toyama (Japan). Hydrogen Isotope Research Center
Shizuoka Univ., Shizuoka (Japan)

Publication Date:: Sun Sep 01 00:00:00 EDT 2019

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE Office of Science (SC)

OSTI Identifier:: 1564143

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Fusion Engineering and Design

Additional Journal Information:: Journal Volume: 146; Journal Issue: PB; Journal ID: ISSN 0920-3796

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Tungsten; Neutron; Divertor; TDS

Citation Formats


                    Kobayashi, Makoto, Shimada, Masashi, Taylor, Chase N., Buchenauer, Dean, Kolasinski, Robert, Koyanagi, Takaaki, Nobuta, Yuji, Hatano, Yuji, and Oya, Yasuhisa. Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron.  United States: N. p., 2019. 
Web.  doi:10.1016/j.fusengdes.2019.03.003.

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                    Kobayashi, Makoto, Shimada, Masashi, Taylor, Chase N., Buchenauer, Dean, Kolasinski, Robert, Koyanagi, Takaaki, Nobuta, Yuji, Hatano, Yuji, & Oya, Yasuhisa. Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron.  United States.  https://doi.org/10.1016/j.fusengdes.2019.03.003

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                    Kobayashi, Makoto, Shimada, Masashi, Taylor, Chase N., Buchenauer, Dean, Kolasinski, Robert, Koyanagi, Takaaki, Nobuta, Yuji, Hatano, Yuji, and Oya, Yasuhisa. Sun .  
"Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron".  United States.  https://doi.org/10.1016/j.fusengdes.2019.03.003.  https://www.osti.gov/servlets/purl/1564143.

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@article{osti_1564143,

  title        = {Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron},

  author       = {Kobayashi, Makoto and Shimada, Masashi and Taylor, Chase N. and Buchenauer, Dean and Kolasinski, Robert and Koyanagi, Takaaki and Nobuta, Yuji and Hatano, Yuji and Oya, Yasuhisa},

  abstractNote = {Tungsten (W) samples were damaged by neutron and 6.4 MeV Fe-ion irradiation above 1000 K simulating the divertor operation temperature. Deuterium (D) retention properties were examined by decorating the damaged W with D and subsequent thermal desorption spectroscopy (TDS) measurements. Vacancy clusters were the major D trapping site in the W irradiated with Fe-ion at 873 K, although D retention by vacancy clusters decreased in the W irradiated with Fe-ion at 1173 K due to dynamic annealing. The D de-trapping activation energy from vacancy clusters was found to be 1.85 eV. D retention in neutron damage W was larger than that damaged by Fe-ion due to the uniform distribution of irradiation defects. The D desorption behaviors from neutron damaged W was simulated well by assuming the D de-trapping activation energy to be 1.52 eV.},

  doi          = {10.1016/j.fusengdes.2019.03.003},

  journal      = {Fusion Engineering and Design},

  number       = PB,

  volume       = 146,

  place        = {United States},

  year         = {Sun Sep 01 00:00:00 EDT 2019},

  month        = {Sun Sep 01 00:00:00 EDT 2019}

}

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