D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation

Oya, Y.; Sun, F.; Yamauchi, Y.; Nobuta, Y.; Shimada, M.; Taylor, C. N.; Wampler, W. R.; Nakata, M.; Garrison, L. M.; Hatano, Y.

doi:10.1016/j.jnucmat.2020.152323

D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation

Journal Article · Tue Jun 23 00:00:00 EDT 2020 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2020.152323· OSTI ID:1650148

Oya, Y. ^[1]; Sun, F. ^[1]; Yamauchi, Y. ^[2]; Nobuta, Y. ^[2]; Shimada, M. ^[3]; Taylor, C. N. ^[3]; Wampler, W. R. ^[4]; Nakata, M. ^[1]; Garrison, L. M. ^[5]; Hatano, Y. ^[6]

Shizuoka Univ. (Japan)
Hokkaido Univ., Sapporo (Japan)
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Toyama (Japan)

Single crystalline W (tungsten) samples irradiated at 633, 963 and 1073 K by neutrons to a damage level of 0.1 dpa were exposed to a high-flux D (deuterium) plasma at 673, 873 and 973 K, respectively, in TPE (Tritium Plasma Experiment) at INL (Idaho National Laboratory). Deuterium desorption was analyzed by TDS (Thermal Desorption Spectroscopy), and D depth profiles were determined by NRA (Nuclear Reaction Analysis) at SNL (Sandia National Laboratories). HIDT (Hydrogen Isotope Diffusion and Trapping) simulation code was applied to evaluate D behavior for neutron-damaged W at higher temperature. The D retention at depths up to 3 f.tm for the neutron-damaged sample at 673 K was two orders of magnitude larger than that for undamaged tungsten, and its D desorption spectrum had a single broad stage at around 900 K. As the neutron irradiation/plasma exposure temperature increased, D retention was largely reduced, and the desorption temperature was increased to higher temperatures above 1100 K. The D depth profiles by NRA also showed D migration toward bulk by higher temperature irradiation, compared to undamaged W. The HIDT simulation indicated that the major binding energy of D was changed from 1.43 eV to 2.07 eV at higher neutron irradiation and plasma exposure temperatures, suggesting that some vacancies and small vacancy clusters would aggregate to form larger voids, or depopulation of weak traps at high D plasma exposure temperatures. It can be said that more stable trapping sites played dominant roles in the D retention at higher neutron irradiation and plasma exposure temperature. The binding energy by HIDT simulation was almost consistent with the reported value by TMAP, but the consideration of not only total D retention measured by TDS but also D depth profile by NRA led to the more accurate D behavior in neutron-damaged W.

View Accepted Manuscript (DOE)

Research Organization:: Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE National Nuclear Security Administration (NNSA)

Grant/Contract Number:: AC04-94AL85000; NA0003525

OSTI ID:: 1650148

Alternate ID(s):: OSTI ID: 1691939

Report Number(s):: SAND--2020-7951J; 687810

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 539; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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36 MATERIALS SCIENCE
HIDT
NRA
Single crystal tungsten
TDS
deuterium retention
neutron irradiation
nuclear fusion

D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation

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