Low-temperature radiation embrittlement of copper alloys
Open accessIntegrity signals
Registry
Cites
Statistics
Claims the paper makes
Claims other papers make about this one
Each is checked against this paper’s own text: does it say what the citing paper says it does?
Copper cryo-stability is not guaranteed under irradiation, and copper alloys have demonstrated severe thermal diffusivity degradation and embrittlement post-cryogenic irradiation.
“But these notions of copper cryo-stability are not guaranteed under the effects of irradiation, and copper alloys have demonstrated severe thermal diffusivity degradation and embrittlement post-cryogenic irradiation [27].”
From A facility for thermo-mechanical characterization of fusion magnet materials during cryogenic ion irradiation (2025) · cites this paper as [27]
The citation lists haven’t been fetched yet
References 10 · Cited by 46
- Authors
- Fabritsiev, S. A., Pokrovsky, A. S., Zinkle, S. J., & Edwards, D. J.
- Affiliations
- State Scientific Center - Research Institute of Atomic Reactors (RU)
- Oak Ridge National Laboratory (US)
- Pacific Northwest National Laboratory (US)
- Corresponding author
- Zinkle, S.J.
- Venue
- Journal of Nuclear Materials
- Publisher
- Elsevier BV
- Published
- 1996-10
- Volume
- 233-237
- Pages
- 513-518
- ISSN
- 0022-3115 (ISSN-L)
- OpenAlex
- W2047701611
- Cited by
- 46
- References
- 10
- Citations by year
- 2026: 1 · 2025: 1 · 2024: 1 · 2023: 1 · 2022: 1 · 2021: 3 · 2020: 1 · 2018: 2 · 2017: 1 · 2016: 2 · 2015: 1 · 2013: 1
- FWCI
- 3.04
- Type
- journal article
- Language
- en
- Open access
- green
- www.osti.gov
- Locations
- Journal of Nuclear Materials (publishedVersion)
- University of North Texas Digital Library (University of North Texas) (submittedVersion)
- OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) (submittedVersion)
- Funders
- Battelle
- Fusion for Energy
- U.S. Department of Energy (DE-AC06-76RL0 1830w)
- Topics
- Physical Sciences › Materials Science › Materials Chemistry › Fusion materials and technologies
- Physical Sciences › Materials Science › Materials Chemistry › Nuclear materials and radiation effects
- Physical Sciences › Materials Science › Materials Chemistry › Nuclear Materials and Properties
- Keywords
- irradiation embrittlement, copper alloys, low-temperature irradiation, fission neutrons, dispersion-strengthened copper, tensile properties, irradiation hardening, fusion reactor structural materials, operating temperature limits, displacement per atom
About these checks
Registry, retraction, Cites and statistics results are computed, not judged, with one exception: a printed reference that no index lists is read once by a model before it counts as a citation error. Claims are extracted by a model and kept only when their quote appears verbatim in the text; each cited source is then checked, with a model’s help, for whether it says what the claim relies on. Those verdicts can be wrong — read the claim’s quote and the cited source before relying on one.
Statistics and arithmetic are recomputed, not judged.
Confidence bands are shown only for fields calibrated on our annotated test set. None is calibrated yet, so no band is shown.
What counts as a claim ›How we measure confidence ›How we check this ›
Are you an author, or do you see a problem with this page? Request a review