Zobrazeno 1 - 10
of 37
pro vyhledávání: '"Hiroki YADA"'
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 5, Iss 4, Pp 18-00083-18-00083 (2018)
The loss-of-reactor-level (LORL) where the coolant circulation path is lost is one of the important accident types of loss-of-heat-removal-system (LOHRS) in loop-type sodium-cooled fast reactors (SFRs). Due to the non-negligible possibility obtained
Externí odkaz:
https://doaj.org/article/a486bebe15b44c138dfe0034be268f2d
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:
The Proceedings of Mechanical Engineering Congress, Japan. 2022:J012-04
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
Autor:
Kosuke Aizawa, Masanori Ando, Takashi Ashida, Yoshitaka Chikazawa, Norihiro Doda, Yasuhiro Enuma, Toshiki Ezure, Yoshitaka Fukano, Yoji Gondai, Erina Hamase, Ryuta Hashidate, Taira Hazama, Shun Hirooka, Tomoyuki Hiyama, Masaki Inoue, Katsunori Ishii, Hiroki Ishikawa, Masaru Ishimaru, Kazunori Isozaki, Wataru Itagaki, Chikara Ito, Hiroyuki Kageyam, Takeji Kaito, Masatoshi Kameyama, Hideki Kamide, Kenji Kamiyama, Atsushi Kato, Hirotaka Kawahara, Shodai Kawakami, Norihiro Kikuchi, Jun Kobayashi, Shoji Kotake, Shigenobu Kubo, Akikazu Kurihara, Shigetaka Maeda, Shuhei Maruyama, Kentaro Matsushita, Masanobu Michino, Takero Mori, Kazuki Morishita, Koji Morita, Hiroyuki Naito, Hiroaki Ohira, Shigeo Ohki, Shuji Ohno, Masaki Okagaki, Satoshi Okajima, Yasushi Okano, Takashi Onishi, Takashi Onizawa, Ayako Ono, Shoji Ono, Takayuki Ozawa, Hiroto Saito, Aaru Sano, Yuichi Sano, Shinji Sasaki, Hiroshi Seino, Akiyuki Seki, Yuta Shizukawa, Misao Takamatsu, Kazuya Takano, Takashi Takata, Shigeru Takaya, Masayuki Takeuchi, Masaaki Tanaka, Hiroshi Taninaka, Takashi Tanno, Kodai Toyota, Akihiro Uchibori, Tomoyuki Uwaba, Takashi Wakai, Tomoyoshi Watakabe, Hiroki Yada, Tomohiko Yamamoto, Hidemasa Yamano, Keisuke Yokoyama, Kenji Yokoyama, Akihiro Yoshida, Ryuji Yoshikawa, Kazuo Yoshimura
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b2adb4e94e5c20e92ba40d6b7a82a146
https://doi.org/10.1016/b978-0-12-824076-2.09992-2
https://doi.org/10.1016/b978-0-12-824076-2.09992-2
Publikováno v:
Volume 1: Codes and Standards.
The leak before break (LBB) assessment guidelines for sodium cooled fast reactors (SFRs) is being developed in the Japan Society of Mechanical Engineers (JSME). The major purpose of the guidelines is to provide LBB assessment procedures for pipes and
Publikováno v:
The Proceedings of Mechanical Engineering Congress, Japan. 2022:J012-03