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Reduced deuterium retention in simultaneously damaged and annealed tungsten

Journal Article · · Journal of Nuclear Materials
 [1];  [2];  [3];  [1];  [1];  [1];  [4]
  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)

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.

Research Organization:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Univ. of California, San Diego, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24); Univ. of California (United States)
Grant/Contract Number:
AC52-06NA25396; FG02-07ER54912; SC0001999
OSTI ID:
1440451
Alternate ID(s):
OSTI ID: 1550188
Report Number(s):
LA-UR--18-21487
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 494; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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