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Abstract: The nuclear industry demands analyses that make possible the long-term operation of nuclear power plants (i.e., beyond 40 years). In this sense, one of the main challenges to overcome is the restricted amount of material available to extend the surveillance programs. To mitigate this issue, mini-CT specimens have been proposed for the evaluation of the fracture properties of reactor pressure vessel (RPV) materials, and particularly, the corresponding Master Curve. These specimens can be taken from the broken halves of previously tested Charpy specimens. In this work, mini-CT specimens have been employed to evaluate the reference temperature of the RPV ANP-5 steel in non-irradiated conditions. The results were compared with those obtained by means of conventional fracture tests.
Authorship: Sánchez M., Cicero S., Arroyo B., Arrieta S.,
Congress: European Conference on Fracture: ECF23 (23ª : 2022 : Funchal, Portugal)
Publisher: Elsevier B.V.
Year of publication: 2022
No. of pages: 6
Publication type: Conference object
DOI: 10.1016/j.prostr.2022.12.027
ISSN: 2452-3216
Publication Url: https://doi.org/10.1016/j.prostr.2022.12.027
UCrea Repository Read publication
MARCOS SÁNCHEZ MATÍAS
SERGIO CICERO GONZALEZ
BORJA ARROYO MARTINEZ
SERGIO ARRIETA GOMEZ
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