Zobrazeno 1 - 10
of 127
pro vyhledávání: '"Katsumasa Miyazaki"'
Autor:
Fuminori IWAMATSU, Katsumasa MIYAZAKI
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 88, Iss 915, Pp 22-00225-22-00225 (2022)
Stress corrosion cracking (SCC) has been detected in the welded components of nuclear power plants. The components of nuclear power plants consist of highly ductile materials such as austenitic stainless steels, and their failure mode is expected to
Externí odkaz:
https://doaj.org/article/2c75223c2ef94e7d82cc03111a977ec4
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 88, Iss 906, Pp 21-00301-21-00301 (2022)
The thermal shrinkage technique, which uses shrinkage strain and shrinkage zone to calculate welding distortion, is expected as a simple simulation to predict the welding distortion of large weld structures. In previous studies, parametric study was
Externí odkaz:
https://doaj.org/article/362e58fb35f042f99f2a0298c76b3d1e
Autor:
Kazuma HIROSAKA, Hidekazu TAKAZAWA, Katsumasa MIYAZAKI, Norihide TOHYAMA, Hiroyuki NOJI, Naomi MATSUMOTO
Publikováno v:
Mechanical Engineering Journal, Vol 6, Iss 6, Pp 19-00222-19-00222 (2019)
Aircraft impact analysis is needed for safety assessment of nuclear power plants. One of the items which should be analyzed for aircraft impact is physical damage to a reinforced concrete (RC) building and this can be estimated by numerical simulatio
Externí odkaz:
https://doaj.org/article/5b1db7c5435b486d9a283572b7c252b8
Publikováno v:
Mechanical Engineering Journal, Vol 3, Iss 6, Pp 16-00300-16-00300 (2016)
Our goal for this study was to understand the cause of the differences in surface properties between surfaces processed using water jet peening (WJP) and shot peening (SP) and to examine the compressive residual stress introduction process with low p
Externí odkaz:
https://doaj.org/article/a8d62a560a90421ebccd13fdfd7e7b9e
Publikováno v:
Mechanical Engineering Journal, Vol 3, Iss 3, Pp 15-00683-15-00683 (2016)
A safety assessment needs to be conducted to analyze the damage caused by an aircraft impacting into a concrete structure at a nuclear power plant. One of the analytical methods used for this issue is a numerical impact simulation conducted after air
Externí odkaz:
https://doaj.org/article/8d0f3812fb294c2fa1f4a7a1b8cf3ab1
Autor:
Masahiro Ito, Kenya Ohashi, Kazumi Fujii, Kyoko Hombo, Katsumasa Miyazaki, Azusa Ooi, Eiji Tada, Atsushi Nishikata
Publikováno v:
ISIJ International. 62:568-576
Publikováno v:
ISIJ International. 61:2143-2149
Fitness-for-Service (FFS) codes, such as ASME Boiler and Pressure Vessels Code, Section XI, have flaw characterization rules for evaluation of structural integrity. Since stress corrosion cracking (SCC) and thermal fatigue frequently cause multiple f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f70a695005ab20b39c059028db589928
https://doi.org/10.1115/1.0000268v
https://doi.org/10.1115/1.0000268v
Autor:
Kazuma Hirosaka, Norihide Tohyama, Hidekazu Takazawa, Naomi Matsumoto, Satoshi Saigo, Katsumasa Miyazaki
Publikováno v:
International Journal of Pressure Vessels and Piping. 167:66-71
Safety assessment methods for evaluating the effect of an aircraft impacting a reinforced concrete (RC) structure at a nuclear power plant are required. The damage behavior of an RC wall during aircraft impact would be simulated by finite element ana
Autor:
Hisamitsu Hato, Katsumasa Miyazaki, Kiyotaka Masaki, Ryujiro Udo, Hiroshi Numakura, Hideaki Nishikawa
Publikováno v:
Tetsu-to-Hagane. 103:201-207