Zobrazeno 1 - 10
of 33
pro vyhledávání: '"Hans-Peter Seifert"'
Autor:
Stefan Ritter, Hans-Peter Seifert
Publikováno v:
Corrosion and Materials Degradation, Vol 3, Iss 2, Pp 178-191 (2022)
Low-alloy reactor pressure vessel steels have a rather low susceptibility to stress corrosion cracking (SCC) in a boiling water reactor (BWR) environment if the high-temperature water contains no anionic impurities. Recent investigations revealed tha
Externí odkaz:
https://doaj.org/article/25c39e7105204705989e20ffb0c73164
Autor:
Hans-Peter Seifert, Stefan Ritter
Publikováno v:
CHIMIA, Vol 59, Iss 12 (2005)
The environmentally assisted initiation and propagation of cracks in structural materials is one of the most important degradation and ageing mechanisms in light water reactors (LWR) and may seriously affect plant availability and economics. In the f
Externí odkaz:
https://doaj.org/article/84c816cec6ba4863a6954d18f96b1c39
Autor:
Kai Chen, Adrianna Mackiewicz, Sannakaisa Virtanen, Pascal V. Grundler, Hans-Peter Seifert, Stefan Ritter
Publikováno v:
Corrosion Reviews. 41:387-398
The effect of zinc (Zn) injection on the stress corrosion cracking (SCC) initiation of an Alloy 182 weld metal and a 20% cold-worked (CW) type 316L stainless steel was investigated under simulated light water reactor conditions. Accelerated SCC initi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8ba7e0622dbac1c3e597d54a84e1d4c2
https://doi.org/10.1515/corrrev-2022-0098
https://doi.org/10.1515/corrrev-2022-0098
Publikováno v:
Que, Z, Seifert, H P, Mazánová, V & Spätig, P 2022, ' Hydrogen embrittlement on fracture resistance of low-alloy reactor pressure vessel steel with high dynamic strain aging at 288 °C ', Materials Letters, vol. 308, 131269 . https://doi.org/10.1016/j.matlet.2021.131269
Fracture mechanics tests in hydrogenated high-temperature water at 288 °C on low-alloy reactor pressure vessel steel with high dynamic strain aging (DSA) susceptibility revealed reduced fracture resistance, accelerated crack growth and increased qua
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1c09b199384f5eb257257a37cf7ab5c8
https://doi.org/10.1016/j.matlet.2021.131269
https://doi.org/10.1016/j.matlet.2021.131269
Publikováno v:
Key Engineering Materials. 827:294-299
Three point bending and impact tests with sub-sized Charpy specimens were performed on the JRQ reference steel for reactor pressure vessels. Quasi-static and dynamic fracture toughness data were calculated and the fracture behavior in the ductile to
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6c2096febeb986a48ad1f92fe441a13d
https://doi.org/10.4028/www.scientific.net/kem.827.294
https://doi.org/10.4028/www.scientific.net/kem.827.294
Autor:
Johannes Bertsch, Hans-Peter Seifert
Publikováno v:
Génie nucléaire.
Les problemes de materiaux et de corrosion dans le circuit de refroidissement primaire des reacteurs nucleaires a eau bouillante (REB) sont passes ici en revue. Le vieillissement et la degradation des materiaux induits par l'exploitation dus a la cor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9d6fea765c2338fb17c8dc56e5c0fe3b
https://doi.org/10.51257/a-v1-bn3762
https://doi.org/10.51257/a-v1-bn3762
Autor:
Stefan Ritter, Hans-Peter Seifert
Publikováno v:
Nuclear corrosion: research, progress and challenges
Carbon and low-alloy steels are widely used for pressure vessels and piping in both the primary and secondary coolant circuits of light water reactors. Some of these components are very critical systems with regard to plant safety and lifetime (exten
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::131db79fc65d0b372f27475846a852f1
https://doi.org/10.1016/b978-0-12-823719-9.00005-6
https://doi.org/10.1016/b978-0-12-823719-9.00005-6
Autor:
Peter L. Andresen, Fanny Balbaud-Célérier, Jean-Louis Courouau, Nikitas Diomidis, Ulla Ehrnstén, Damien Féron, Antti Forsström, Elodie Gipon, Dolores Gómez-Briceño, Nathalie Gruet, David Guzonas, Benoit Gwinner, Hannu Hänninen, Fraser King, Pierre Laghoutaris, Laure Martinelli, Radek Novotny, Cristiano Padovani, Francisco J. Perosanz, Stefan Ritter, Fabien Rouillard, Hans-Peter Seifert, Stéphane Trevin, Marc Tupin, Gary S. Was, Yuriy Yagodzinskyy
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::74827b2eda026fd5eca4ff3ad26c6f84
https://doi.org/10.1016/b978-0-12-823719-9.00022-6
https://doi.org/10.1016/b978-0-12-823719-9.00022-6
Publikováno v:
Comprehensive nuclear materials
This chapter reviews the uniform and localized corrosion behavior of carbon and low-alloy-steel pressure-boundary components in the primary and secondary coolant systems of water-cooled reactors and covers experimental and theoretical background know
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b696ebb31553c7d6d723a9aa009f5204
https://doi.org/10.1016/b978-0-12-803581-8.11763-1
https://doi.org/10.1016/b978-0-12-803581-8.11763-1