Surface chemistry of neutron irradiated tungsten in a high-temperature multi-material environment☆

Chase N. Taylor, Masashi Shimada, Yuji Nobuta, Makoto I. Kobayashi, Yasuhisa Oya, Yuji Hatano, Takaaki Koyanagi

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Abstract

Deuterium retention was measured on neutron irradiated tungsten samples where one side of the samples had a visually clean metallic luster and the opposite side appeared to have a reacted surface film. Deuterium plasma exposure and subsequent thermal desorption from the reacted surface side produced spectra with larger total deuterium desorption at lower temperatures than from the clean surface side. For neutron irradiation, these W disk samples were installed in an irradiation capsule in such a way that one side of W sample was in contact with the surface of another W sample, and the opposite side was in contact with a SiC temperature monitor. The composition of the reacted surface was investigated using X-ray photoelectron spectroscopy and showed that SiC had interdiffused into the W samples. Neutron enhanced diffusion likely contributed to this as SiC and W are stable at temperatures exceeding the irradiation temperature. Results highlight the need to consider the surface chemistry of samples in drawing conclusions on hydrogen isotope retention of W materials and also illustrate the complexity of multi-material nuclear environments expected in fusion devices.

Original languageEnglish
Article number101323
JournalNuclear Materials and Energy
Volume34
DOIs
StatePublished - Mar 2023

Funding

We thank A. Hasegawa for the preparation of W specimens. This work was prepared for the U.S. Department of Energy, Office of Fusion Energy Sciences, under the DOE Idaho Field Office contract number DE-AC07–05ID14517. This work was part of the US-Japan collaborative research projects, PHENIX and FRONTIER. Neutron irradiation was supported by the US Department of Energy, Office of Fusion Energy Sciences under contract DE-AC05-00OR22725 with UT-Battelle LCC. A portion of this research used resources at the High Flux Isotope Reactor, a DOE Office of Science User Facility operated by ORNL. * Notice: This manuscript has been co-authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( https://energy.gov/downloads/doe-public-access-plan ).

FundersFunder number
PHENIX
U.S. Department of EnergyDE-AC05-00OR22725, DE-AC07–05ID14517
Office of Science
Fusion Energy Sciences
Oak Ridge National Laboratory
UT-Battelle
Frontiers Clinical and Translational Science Institute, University of Kansas

    Keywords

    • Deuterium retention
    • Neutron irradiated tungsten
    • Surface chemistry
    • X-ray photoelectron spectroscopy

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