Zobrazeno 1 - 10
of 13
pro vyhledávání: '"Francisco Javier Perosanz"'
Autor:
Sergio Arrieta, Francisco Javier Perosanz, Jose Miguel Barcala, Maria Luisa Ruiz, Sergio Cicero
Publikováno v:
Metals, Vol 12, Iss 12, p 2091 (2022)
The direct current potential drop (DCPD) technique may be used in crack propagation tests to measure the crack growth rate (CGR). Potential probes attached to the specimen allow the variation of the crack length to be estimated. In this research, the
Externí odkaz:
https://doaj.org/article/74108cbd91dc42d59d2c8773c001c390
Autor:
Matthias Bruchhausen, Gintautas Dundulis, Alec McLennan, Sergio Arrieta, Tim Austin, Román Cicero, Walter-John Chitty, Luc Doremus, Miroslava Ernestova, Albertas Grybenas, Caitlin Huotilainen, Jonathan Mann, Kevin Mottershead, Radek Novotny, Francisco Javier Perosanz, Norman Platts, Jean-Christophe le Roux, Philippe Spätig, Claudia Torre Celeizábal, Marius Twite, Marc Vankeerberghen
Publikováno v:
Metals, Vol 11, Iss 2, p 307 (2021)
A substantial amount of research effort has been applied to the field of environmentally assisted fatigue (EAF) due to the requirement to account for the EAF behaviour of metals for existing and new build nuclear power plants. We present the results
Externí odkaz:
https://doaj.org/article/40f5530529f54b26bcb39f760bd66a16
Autor:
María del Pilar Fernández, Jesús Peña, Ana María Lancha, Francisco Javier Perosanz, Marta Navas
Publikováno v:
Revista de Metalurgia, Vol 36, Iss 1, Pp 13-23 (2000)
Las soldaduras disímiles, que son utilizadas para unir diferentes partes en los reactores de agua ligera, son potencialmente susceptibles de experimentar corrosión bajo tensión (SCC) en los medios acuosos característicos de las plantas nucleares.
Externí odkaz:
https://doaj.org/article/d8c0d3e05d1a41e3a294e55e97d216b3
Publikováno v:
EPJ Nuclear Sciences & Technologies
Research to better understand the phenomena influencing materials and components’ performance is important for increasing the safety of Generation II and III nuclear plants. A crucial step for improving nuclear safety is the development of new expe
Autor:
Jonathan Duff, Yuchen Gu, M. Grace Burke, Fabio Scenini, Bojan Zajec, Renate Kilian, Radek Novotny, Francisco Javier Perosanz, Stefan Ritter, Andraž Legat, Rik Wouter Bosch, Matthias Herbst, Alice Dinu, Ulla Ehrnstén, Aki Toivonen, Oliver Martin
Publikováno v:
Bosch, R W, Ritter, S, Herbst, M, Kilian, R, Burke, M G, Duff, J, Scenini, F, Gu, Y, Dinu, A, Ehrnstén, U, Toivonen, A, Novotny, R, Martin, O, Perosanz, F J, Legat, A & Zajec, B 2021, ' Stress corrosion crack initiation testing with tapered specimens in high-temperature water–results of a collaborative research project ', Corrosion Engineering Science and Technology, vol. 56, no. 2, pp. 103-118 . https://doi.org/10.1080/1478422X.2020.1815460
The applicability of an accelerated test technique using tapered tensile specimens for investigating the stress corrosion crack (SCC) initiation behaviour of structural materials in high-temperature water was assessed in the framework of a European c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b6d0b7094c42238b42b4325e3606d339
https://cronfa.swan.ac.uk/Record/cronfa57703/Download/57703__20711__308640e72ef74b6daaaee0f829c6e1d9.pdf
https://cronfa.swan.ac.uk/Record/cronfa57703/Download/57703__20711__308640e72ef74b6daaaee0f829c6e1d9.pdf
Autor:
Francisco Javier Perosanz, Alberto Sáez-Maderuelo, Patricie Halodová, María Luisa Ruiz-Lorenzo, Jan Procházka, Hygreeva Kiran Namburi
Publikováno v:
Volume 6: Materials and Fabrication.
Alloy 690, which was designed as a replacement for the Alloy 600, is widely used in the nuclear industry due to its optimum behavior to stress corrosion cracking (SCC) under nuclear reactor operating conditions. Because of this superior resistance, a
Autor:
Marta Navas, Francisco Javier Perosanz, Ana María Lancha, María del Pilar Fernández, Jesús Peña
Publikováno v:
Revista de Metalurgia, Vol 36, Iss 1, Pp 13-23 (2000)
Dissimilar welds, used to join different sections in light water reactors, are potentially susceptible to stress corrosion cracking (SCC) in aqueous mediums characteristic of nuclear plants. However, the study of these welds has been limited to evalu
Publikováno v:
Scopus-Elsevier
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::798b773974848811e584b9cd6b1da96f
http://www.scopus.com/inward/record.url?eid=2-s2.0-0342322957&partnerID=MN8TOARS
http://www.scopus.com/inward/record.url?eid=2-s2.0-0342322957&partnerID=MN8TOARS
Publikováno v:
Scopus-Elsevier
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::475f72991862296e0c5978b4681c68f4
http://www.scopus.com/inward/record.url?eid=2-s2.0-0031343287&partnerID=MN8TOARS
http://www.scopus.com/inward/record.url?eid=2-s2.0-0031343287&partnerID=MN8TOARS
Autor:
Gómez-Briceño, D., Lapeña, J., García, M. S., Castro, L., Francisco Javier Perosanz, Ahluwalia, K., Hickling, J.
Publikováno v:
Scopus-Elsevier
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::2d41ed1a052e50ee204777f22c9fdccc
http://www.scopus.com/inward/record.url?eid=2-s2.0-78649390267&partnerID=MN8TOARS
http://www.scopus.com/inward/record.url?eid=2-s2.0-78649390267&partnerID=MN8TOARS