Reduced deuterium retention in simultaneously damaged and annealed tungsten

Simmonds, M. J.; Wang, Y. Q.; Barton, J. L.; Baldwin, M. J.; Yu, J. H.; Doerner, R. P.; Tynan, G. R.

doi:10.1016/j.jnucmat.2017.06.010

Reduced deuterium retention in simultaneously damaged and annealed tungsten

Journal Article · Sat Jun 24 00:00:00 EDT 2017 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2017.06.010· OSTI ID:1440451

Simmonds, M. J. ^[1]; Wang, Y. Q. ^[2]; Barton, J. L. ^[3]; Baldwin, M. J. ^[1]; Yu, J. H. ^[1]; Doerner, R. P. ^[1]; Tynan, G. R. ^[4]

Univ. of California, San Diego, CA (United States). Center for Energy Research
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sandia National Lab. (SNL-CA), Livermore, CA (United States). Energy Innovation Dept.
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.

View Accepted Manuscript (DOE)

Research Organization:: Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Univ. of California, San Diego, CA (United States)

Sponsoring Organization:: USDOE; 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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TEM studies of 1 MeV Fe ⁺ ion-irradiated W alloys by wet chemical method: high-temperature annealing and deuterium retention Ding, Xiao-Yu; Liu, Jia-Qin; Luo, Lai-Ma Nuclear Fusion, Vol. 59, Issue 1 https://doi.org/10.1088/1741-4326/aaeaee	journal	November 2018
Ion beam analysis of fusion plasma-facing materials and components: facilities and research challenges Mayer, M.; Möller, S.; Rubel, M. Nuclear Fusion, Vol. 60, Issue 2 https://doi.org/10.1088/1741-4326/ab5817	journal	December 2019

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36 MATERIALS SCIENCE
NRA
TDS
concurrent ion beam damage
deuterium
dynamic annealing
recovery
retention
tungsten

Reduced deuterium retention in simultaneously damaged and annealed tungsten

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