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        <datestamp>2023-05-15T18:22:28Z</datestamp>
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          <dc:title>Neutron irradiation-enhanced grain growth in tungsten and tungsten alloys</dc:title>
          <jpcoar:creator>
            <jpcoar:creatorName>Gietl, Hanns</jpcoar:creatorName>
          </jpcoar:creator>
          <jpcoar:creator>
            <jpcoar:creatorName>Koyanagi, Takaaki</jpcoar:creatorName>
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          <jpcoar:creator>
            <jpcoar:creatorName>Hu, Xunxiang</jpcoar:creatorName>
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          <jpcoar:creator>
            <jpcoar:creatorName>Fukuda, Makoto</jpcoar:creatorName>
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          <jpcoar:creator>
            <jpcoar:creatorName>Hasegawa, Akira</jpcoar:creatorName>
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          <jpcoar:creator>
            <jpcoar:creatorName>Katoh, Yutai</jpcoar:creatorName>
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          <jpcoar:creator>
            <jpcoar:creatorName xml:lang="en">Makoto, Fukuda</jpcoar:creatorName>
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          <datacite:description descriptionType="Abstract">To understand the microstructural stability of candidate plasma-facing materials under fusion-relevant environments, neutron irradiation of W and W-3%Re alloys with and without K and La dopants was per formed in the mixed-spectrum High Flux Isotope Reactor at nominal temperatures of ~850 °C and ~1100 °C to calculated doses between 0.42 and 0.47 dpa. To the best of our knowledge, this study presents the first experimental evidence of radiation-enhanced recrystallization in W and undoped W–Re alloys at ~850 °C, conditions where thermal annealing does not cause any grain growth in a similar timescale. Potassium- or lanthanum-doped tungsten alloys showed more resistance to radiation-enhanced grain growth. We explain the acceleration of grain growth by analyzing the self-diffusion constant under atomic displacement environments. The microstructural observations of the studied W variants suggest that La doping is more effective than K doping for mitigating recrystallization. This study also found that radiation-enhanced crystallization is an important consideration when designing and applying W to plasma-facing components in future nuclear fusion reactors.</datacite:description>
          <dc:publisher>Elsevier</dc:publisher>
          <datacite:date dateType="Issued">2021-12</datacite:date>
          <dc:language>eng</dc:language>
          <dc:type rdf:resource="http://purl.org/coar/resource_type/c_6501">journal article</dc:type>
          <jpcoar:identifier identifierType="URI">https://repo.qst.go.jp/records/84518</jpcoar:identifier>
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            <jpcoar:relatedIdentifier identifierType="DOI">10.1016/j.jallcom.2021.163419</jpcoar:relatedIdentifier>
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            <jpcoar:relatedIdentifier identifierType="URI">https://www.sciencedirect.com/science/article/abs/pii/S0925838821048295?via%3Dihub</jpcoar:relatedIdentifier>
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          <jpcoar:sourceIdentifier identifierType="ISSN">0925-8388</jpcoar:sourceIdentifier>
          <jpcoar:sourceTitle>Journal of Alloys and Compounds</jpcoar:sourceTitle>
          <jpcoar:volume>901</jpcoar:volume>
          <jpcoar:pageStart>163419</jpcoar:pageStart>
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