Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Kensaku ARAI"'
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 89, Iss 925, Pp 23-00046-23-00046 (2023)
Tensile tests were conducted for notched round-bar specimens to acquire the limit conditions of local failure, which is ductile failure after large local deformation for three types of steel, SGV480, SPV490 and SGV410, for nuclear containment structu
Externí odkaz:
https://doaj.org/article/9f255dc11ccd4535925bb3acfae84667
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 89, Iss 924, Pp 23-00070-23-00070 (2023)
A series of tensile tests were conducted for notched plate specimens whose shapes are similar to the pressure shell to clarify the local failure characteristics for the steel nuclear containment. The specimens included the full or partial-width notch
Externí odkaz:
https://doaj.org/article/0423e774fea443968ef923066b813c1d
Publikováno v:
International Journal of Pressure Vessels and Piping. 194:104488
Herein, a tensile test for notched round–bar specimens of two types of carbon steel used in nuclear containment vessels was performed. The test results were analyzed using the Bridgman solution and an elastoplastic finite element method. The analys
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b3881e23ecc88b25ccb4634f1a7c1406
https://doi.org/10.1016/j.ijpvp.2021.104488
https://doi.org/10.1016/j.ijpvp.2021.104488
Publikováno v:
The Proceedings of the Materials and Mechanics Conference. 2021:OS1906
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1e016993604b303f09ec0eaa73ab4dd8
https://doi.org/10.1299/jsmemm.2021.os1906
https://doi.org/10.1299/jsmemm.2021.os1906
Publikováno v:
The Proceedings of the Materials and Mechanics Conference. 2021:OS1907
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::de71299477bed100dabab6f9a4ed3932
https://doi.org/10.1299/jsmemm.2021.os1907
https://doi.org/10.1299/jsmemm.2021.os1907
Publikováno v:
Volume 1B: Codes and Standards.
Reactor pressure vessels (RPVs) in nuclear power plants are important components that prevent non-ductile fracture considering neutron irradiation embrittlement as aging degradation and several types of transients. An analysis code called PASCAL for
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1585e474011e5acc0427125c89447c93
https://doi.org/10.1115/pvp2018-84989
https://doi.org/10.1115/pvp2018-84989