Zobrazeno 1 - 10
of 87
pro vyhledávání: '"Shigeru Takaya"'
Publikováno v:
Mechanical Engineering Journal, Vol 11, Iss 2, Pp 23-00408-23-00408 (2024)
Enhancing the ability to manage abnormal situations is important for improvement of the safety of nuclear power plants. It is necessary to investigate potential risks thoroughly in advance, and prepare countermeasures against the identified risks. In
Externí odkaz:
https://doaj.org/article/37f4f2d7dc844f40be77c59112bcde63
Publikováno v:
Mechanical Engineering Journal, Vol 10, Iss 4, Pp 23-00044-23-00044 (2023)
To develop rationalized maintenance plans for nuclear power plants, the characteristics of each plant must be considered. For sodium-cooled fast reactor (SFR) plants, constraints on inspections exist due to the specialty that equipment retaining sodi
Externí odkaz:
https://doaj.org/article/e9734f10cc6a41ada098153153f1baa6
Publikováno v:
Mechanical Engineering Journal, Vol 7, Iss 4, Pp 19-00570-19-00570 (2020)
To identify functions and facilities that are critical for ensuring safety in advanced reactors, for which only a limited usage history is available, it is necessary to consider the characteristics of each reactor type by utilizing more risk-related
Externí odkaz:
https://doaj.org/article/440339ede4664ef0a2cb384a38d9c45f
Autor:
Shigeru TAKAYA, Naoto SASAKI
Publikováno v:
Mechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00549-19-00549 (2020)
Seismic buckling of vessels is one of main concerns for the design of fast reactor plants in Japan. Rational design is important because of two conflicting requirements; thicker walls are preferable to prevent seismic buckling of vessels, while exces
Externí odkaz:
https://doaj.org/article/5cf46bc69a634982adf1021e752b746f
Autor:
Shigeru TAKAYA, Tatsuya FUJISAKI
Publikováno v:
Mechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00526-19-00526 (2020)
In sodium-cooled fast reactors, free liquid surfaces are found in several important components, including reactor vessels; sloshing due to earthquakes is one of the major concerns in design. Especially in cases where seismic isolation systems are ins
Externí odkaz:
https://doaj.org/article/a183c89060104d9fba0267b2da62bf86
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 84, Iss 859, Pp 17-00389-17-00389 (2017)
In the in-service inspection of sodium cooled fast reactors, an examination by continuous leak monitoring will be applied for components constituting sodium boundaries. The continuous leak monitoring examinations are premises in a LBB (leak before br
Externí odkaz:
https://doaj.org/article/0482c7b84fc24077a221ae14b4a57009
Publikováno v:
Mechanical Engineering Journal, Vol 4, Iss 3, Pp 16-00558-16-00558 (2017)
Seismic buckling of vessels is one of the main concerns for the design of nuclear power plants in Japan. Rational design is important, especially for fast reactor plants. Although thicker walls are preferable in terms of prevention of seismic bucklin
Externí odkaz:
https://doaj.org/article/f5a56de309cd4d2097314854fbf13ba3
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 83, Iss 845, Pp 16-00434-16-00434 (2016)
Probabilistic fracture mechanics (PFM) analysis is an evaluation method for the structural integrity of components containing a crack, with considering the random variability of the input physical parameters, such as crack growth rate. The characteri
Externí odkaz:
https://doaj.org/article/45188200244142b4b634153be231e5aa
Publikováno v:
Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle.
In order to develop rationalized maintenance plans of nuclear power plants, it is necessary to consider characteristics of each plant. For sodium-cooled fast reactor (SFR) plants, there are constraints on inspections due to the specialty that sodium
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::491507fbdbdb733227faa100b68958b7
https://doi.org/10.1115/icone29-90542
https://doi.org/10.1115/icone29-90542
Autor:
Eiichi Wakai, Tomoaki Suzudo, Nariaki Okubo, Masataka Yamaguchi, Yuji Nagae, Hiroaki Abe, Akira Hasegawa, Shuhei Nogami, Takashi Tanno, Shigeru Takaya, Kazumi Aoto
Publikováno v:
Materials Science Forum. 1024:53-69
The effects of helium concentration and displacement damage on microstructural evolution at low dpa and low helium concentration were mainly investigated in specimens of austenitic stainless steel 316FR or SUS304 and a high chromium martensitic steel
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::217375fcfad7f7293c408bb97ad25d4d
https://doi.org/10.4028/www.scientific.net/msf.1024.53
https://doi.org/10.4028/www.scientific.net/msf.1024.53