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Title: Reduced deuterium retention in simultaneously damaged and annealed tungsten

Abstract

Deuterium (D) retention in polycrystalline tungsten (W) with copper (Cu) ion damage concurrently produced at elevated surface temperature is investigated in this paper. An in situ heated stage held W samples at a controlled temperature up to 1243 K, which were subjected to displacement damage produced by 3.4 MeV Cu ions. D retention is subsequently explored by exposure of the W samples held at 383 K to a D2 plasma ion fluence of 1024 D+/m2. Nuclear reaction analysis (NRA), utilizing the D(3He,p)4He nuclear reaction, is used to probe the D concentration in the near surface up to 6 μm. Thermal desorption spectroscopy (TDS) is used to measure outgassed HD and D2 molecules to determine the bulk D concentration. Both NRA and TDS measure a significant reduction in D retention for samples damaged at elevated temperature. TDS quantitatively shows that the lowest energy trap remains largely unaffected while higher energy traps, induced by Cu ions, are annealed and approach intrinsic concentrations as the temperature during ion damage approaches 1243 K. Finally, analysis of TDS data yields an activation energy of (0.10 ± 0.02) eV for recovery of ion-damage induced traps at elevated temperature.

Authors:
 [1];  [2];  [3];  [1];  [1];  [1];  [4]
+ Show Author Affiliations
  1. Univ. of California, San Diego, CA (United States). Center for Energy Research
  2. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  3. Sandia National Lab. (SNL-CA), Livermore, CA (United States). Energy Innovation Dept.
  4. Univ. of California, San Diego, CA (United States). Center for Energy Research. Dept. of Mechanical and Aerospace Engineering (MAE)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Univ. of California, San Diego, CA (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES); Univ. of California (United States)
OSTI Identifier:
1440451
Alternate Identifier(s):
OSTI ID: 1550188
Report Number(s):
LA-UR-18-21487
Journal ID: ISSN 0022-3115; TRN: US1900740
Grant/Contract Number:  
AC52-06NA25396; FG02-07ER54912; SC0001999; 12-LR-237801
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 494; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; tungsten; dynamic annealing; deuterium; retention; recovery; concurrent ion beam damage; NRA; TDS

Citation Formats

Simmonds, M. J., Wang, Y. Q., Barton, J. L., Baldwin, M. J., Yu, J. H., Doerner, R. P., and Tynan, G. R. Reduced deuterium retention in simultaneously damaged and annealed tungsten. United States: N. p., 2017. Web. doi:10.1016/j.jnucmat.2017.06.010.
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Simmonds, M. J., Wang, Y. Q., Barton, J. L., Baldwin, M. J., Yu, J. H., Doerner, R. P., & Tynan, G. R. Reduced deuterium retention in simultaneously damaged and annealed tungsten. United States. https://doi.org/10.1016/j.jnucmat.2017.06.010
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Simmonds, M. J., Wang, Y. Q., Barton, J. L., Baldwin, M. J., Yu, J. H., Doerner, R. P., and Tynan, G. R. Sat . "Reduced deuterium retention in simultaneously damaged and annealed tungsten". United States. https://doi.org/10.1016/j.jnucmat.2017.06.010. https://www.osti.gov/servlets/purl/1440451.
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@article{osti_1440451,
title = {Reduced deuterium retention in simultaneously damaged and annealed tungsten},
author = {Simmonds, M. J. and Wang, Y. Q. and Barton, J. L. and Baldwin, M. J. and Yu, J. H. and Doerner, R. P. and Tynan, G. R.},
abstractNote = {Deuterium (D) retention in polycrystalline tungsten (W) with copper (Cu) ion damage concurrently produced at elevated surface temperature is investigated in this paper. An in situ heated stage held W samples at a controlled temperature up to 1243 K, which were subjected to displacement damage produced by 3.4 MeV Cu ions. D retention is subsequently explored by exposure of the W samples held at 383 K to a D2 plasma ion fluence of 1024 D+/m2. Nuclear reaction analysis (NRA), utilizing the D(3He,p)4He nuclear reaction, is used to probe the D concentration in the near surface up to 6 μm. Thermal desorption spectroscopy (TDS) is used to measure outgassed HD and D2 molecules to determine the bulk D concentration. Both NRA and TDS measure a significant reduction in D retention for samples damaged at elevated temperature. TDS quantitatively shows that the lowest energy trap remains largely unaffected while higher energy traps, induced by Cu ions, are annealed and approach intrinsic concentrations as the temperature during ion damage approaches 1243 K. Finally, analysis of TDS data yields an activation energy of (0.10 ± 0.02) eV for recovery of ion-damage induced traps at elevated temperature.},
doi = {10.1016/j.jnucmat.2017.06.010},
journal = {Journal of Nuclear Materials},
number = ,
volume = 494,
place = {United States},
year = {Sat Jun 24 00:00:00 EDT 2017},
month = {Sat Jun 24 00:00:00 EDT 2017}
}
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https://doi.org/10.1016/j.jnucmat.2017.06.010
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    Works referencing / citing this record:

    TEM studies of 1 MeV Fe + ion-irradiated W alloys by wet chemical method: high-temperature annealing and deuterium retention
    journal, November 2018

    Ion beam analysis of fusion plasma-facing materials and components: facilities and research challenges
    journal, December 2019

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