Zobrazeno 1 - 10 of 73 pro vyhledávání: '"Akikazu KURIHARA"'
1
Akademický článek
Velocity distribution in the subchannels of a pin bundle with a wrapping wire (Evaluation of the Reynolds number dependence in a three-pin bundle)
Autor: Kosuke AIZAWA, Tomoyuki HIYAMA, Masahiro NISHIMURA, Akikazu KURIHARA, Katsuji ISHIDA
Publikováno v: Mechanical Engineering Journal, Vol 8, Iss 4, Pp 20-00547-20-00547 (2021)
A sodium-cooled fast reactor has been designed to attain a high burn-up core in commercialized fast reactor cycle systems. The sodium-cooled fast reactor adopts a wire spacer between fuel pins. The wire spacer performs functions of securing the coola
Externí odkaz: https://doaj.org/article/484c75449e404143a287beb9c99e089f
Zobrazit plný text záznamu
2
Akademický článek
Evaluation of target-wastage in consideration of sodium-water reaction environment formed on the periphery of an adjacent tube in steam generator of sodium-cooled fast reactor
Autor: Akikazu KURIHARA, Ryota UMEDA, Kazuhito SHIMOYAMA, Shin KIKUCHI
Publikováno v: Nihon Kikai Gakkai ronbunshu, Vol 84, Iss 859, Pp 17-00382-17-00382 (2018)
Wastage on adjacent tubes (target-wastage) arise from water/steam leak in steam generators of sodium-cooled fast reactors (sodium-water reaction). Target-wastage is likely to be caused by liquid droplet impingement erosion (LDI) and Na-Fe composite o
Externí odkaz: https://doaj.org/article/ea798ca3f6c64b3fa90439cdce3944da
Zobrazit plný text záznamu
3
Akademický článek
Numerical approach for quantification of selfwastage phenomena in sodium-cooled fast reactor
Autor: Sunghyon Jang, Takashi Takata, Akira Yamaguchi, Akihiro Uchibori, Akikazu Kurihara, Hiroyuki Ohshima
Publikováno v: Nuclear Engineering and Technology, Vol 47, Iss 6, Pp 700-711 (2015)
Sodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer heat from the reactor core. The main hazard associated with sodium is its rapid reaction with water. Sodium–water reaction (SWR) takes place when water or
Externí odkaz: https://doaj.org/article/7dafd9a0e22f4c16b6ab21d8b6275cae
Zobrazit plný text záznamu
4
Velocity distribution in the subchannels of a pin bundle with a wrapping wire (Evaluation of the Reynolds number dependence in a three-pin bundle)
Autor: Katsuji Ishida, Masahiro Nishimura, Tomoyuki Hiyama, Kosuke Aizawa, Akikazu Kurihara
Publikováno v: Mechanical Engineering Journal, Vol 8, Iss 4, Pp 20-00547-20-00547 (2021)
A sodium-cooled fast reactor has been designed to attain a high burn-up core in commercialized fast reactor cycle systems. The sodium-cooled fast reactor adopts a wire spacer between fuel pins. The wire spacer performs functions of securing the coola
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c8ec0ea3864d254d4763a64f6e367d99
https://doi.org/10.1299/mej.20-00547
Zobrazit plný text záznamu
6
Contributors
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
Zobrazit plný text záznamu
7
Experimental Study on Aerosol Transport Behavior in Multiple Cells With Expandable Connecting Pipe for Safety Assessment of Sodium-Cooled Fast Reactors
Autor: Ryota Umeda, Toshiki Kondo, Shin Kikuchi, Akikazu Kurihara
Publikováno v: Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation.
Sodium fire is one of the accidental events in case of sodium leak of sodium-cooled fast reactor. This event is basically the reaction between liquid sodium and oxygen with exothermic heat. The transport behavior of the aerosol as reaction product (s
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::8fe36a1dd1c5d538b6b65fb165915421
https://doi.org/10.1115/icone28-61200
Zobrazit plný text záznamu
8
Investigation on Velocity Distribution in the Subchannels of Pin Bundle With Wrapping Wire: Evaluation of Reynolds Number Dependence in 3-Pin Bundle
Autor: Katsuji Ishida, Masahiro Nishimura, Akikazu Kurihara, Tomoyuki Hiyama, Kosuke Aizawa
Publikováno v: Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation.
A sodium-cooled fast reactor is designed to attain a high burn-up core in commercialized fast reactor cycle systems. In high burn-up fuel subassemblies, the deformation of fuel pin due to the swelling and thermal bowing may decrease local flow veloci
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::bb615a359af437687f0b8f24f5925163
https://doi.org/10.1115/icone2020-16679
Zobrazit plný text záznamu
9
Study on Cooling Process in a Reactor Vessel of Sodium-Cooled Fast Reactor Under Severe Accident: Velocity Measurement Experiments Simulating Operation of Decay Heat Removal Systems
Autor: Yasuhiro Miyake, Mitsuyo Tsuji, Kosuke Aizawa, Akikazu Kurihara, Jun Kobayashi
Publikováno v: Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation.
In Sodium-cooled Fast Reactors (SFRs), it is important to optimize the design and operate decay heat removal systems for safety enhancement against severe accidents which could lead to core melting. It is necessary to remove the decay heat from the m
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5a65d770d5f273cf2a6a769cabf91483
https://doi.org/10.1115/icone2020-16796
Zobrazit plný text záznamu
10
Improvement of steam generator tube failure propagation analysis code LEAP for evaluation of overheating rupture
Autor: Hiroyuki Ohshima, Hideki Yanagisawa, Takashi Takata, Akihiro Uchibori, Hirotsugu Hamada, Akikazu Kurihara
Publikováno v: Journal of Nuclear Science and Technology. 56:201-209
As a part of safety assessment or design of steam generators of sodium-cooled fast reactors, it is necessary to evaluate the water leak rate under sodium–water reaction accident. The computer code called LEAP-II calculating a design basis water lea
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::f2a4b59d7b6be61dab890b872250b350
https://doi.org/10.1080/00223131.2018.1558128
Zobrazit plný text záznamu

Vyhledávací nástroje:

Upřesnit hledání

Omezení vyhledávání
Plný text Recenzováno Digitální knihovna AV ČR
Zdroje