In-situ WB-STEM observation of dislocation loop behavior in reactor pressure vessel steel during post-irradiation annealing

詳細情報 詳細情報について

• CRID

  1360290617731682560

• DOI

  10.1016/j.mtla.2020.100778

• ISSN

  25891529

• Web Site

  https://api.elsevier.com/content/article/PII:S2589152920301952?httpAccept=text/xml

  https://api.elsevier.com/content/article/PII:S2589152920301952?httpAccept=text/plain

• データソース種別

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