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Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.
Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07
This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.
Ino, Kohei*; Hernsdorf, A. W.*; Konno, Yuta*; Kozuka, Mariko*; Yanagawa, Katsunori*; Kato, Shingo*; Sunamura, Michinari*; Hirota, Akinari*; Togo, Yoko*; Ito, Kazumasa*; et al.
ISME Journal, 12(1), p.31 - 47, 2018/01
Times Cited Count：49 Percentile：91.33(Ecology)In this study, we found the dominance ofanaerobic methane-oxidizing archaea in groundwater enriched in sulfate and methane from a 300-m deep underground borehole in granitic rock.
Amano, Katsunori; Enuma, Yasuhiro; Futagami, Satoshi; Inoue, Tomoyuki*; Watanabe, Sota*
Proceedings of 24th International Conference on Nuclear Engineering (ICONE-24) (DVD-ROM), 7 Pages, 2016/06
In the framework of GIF, SDC and SDG for the generation IV SFRs have been developed in the circumstance of worldwide deployment of SFRs. JAEA and MFBR have been investigating design study of an advanced loop-type SFR to satisfy SDC in the feasibility study of SDG for SFR. In this study, the ability of the pump/IHX in the advanced loop-type SFR for the safety measures has been evaluated. In addition to the safety measures, maintainability and reparability are taken into account in the advanced loop-type SFR design study. The pump/IHX has been modified to satisfy these requirements. This paper describes the modifications for the ability to withstand a severe earthquake, the reliability of the guard vessel in the primary coolant leak, and the reliability of expansion joints in a sodium-water reaction. The evaluations of thermal transient, structural vibration with pump rotation and wear-out of IHX tubes, that has been adversely effected by the modifications, were described as well.
Amano, Hikaru; *; Uchida, Shigeo*; Tsuzuki, Katsunori; Matsuoka, Shungo*; Ikeda, Hiroshi*; Matsubara, Takeshi*; Kurosawa, Naohiro*
KURRI-KR-80, p.48 - 49, 2001/12
no abstracts in English
Imamura, Hiroaki; Hayakawa, Masato; Suzuki, Masashi; Chinone, Masaru; Amano, Katsunori; Hirabayashi, Masaru
no journal, ,
no abstracts in English
Amano, Katsunori; Enuma, Yasuhiro; Futagami, Satoshi; Watanabe, Sota*
no journal, ,
no abstracts in English
Amano, Katsunori; Enuma, Yasuhiro; Futagami, Satoshi; Ushiki, Hiroshi*; Kawamura, Masaya*; Ichihara, Takashi*
no journal, ,
no abstracts in English
Suzuki, Masashi; Yoshida, Eiichi; Imamura, Hiroaki; Amano, Katsunori; Shimoyama, Kazuhito
no journal, ,
no abstracts in English
Nabeshima, Kunihiko; Doda, Norihiro; Ishikawa, Nobuyuki; Amano, Katsunori; Ohshima, Hiroyuki
no journal, ,
AtheNa-SA project in JAEA is planned to evaluate the availability of cooling system in the reactor vessel under the severe accident of loop-type or pool-type sodium-cooled fast reactor. This report describes the design study of large scale sodium test facility AtheNa-RV, which could simulate natural circulation decay heat removal system in normal or damaged core.
Amano, Katsunori; Enuma, Yasuhiro; Chikazawa, Yoshitaka; Watanabe, Osamu*; Hayakawa, Satoshi*; Inoue, Tomoyuki*
no journal, ,
no abstracts in English
Tanaka, Masaaki; Amano, Katsunori*; Ishikawa, Nobuyuki; Nabeshima, Kunihiko; Ohshima, Hiroyuki; Oyama, Kazuhiro*; Nakamura, Hironori*; Ichihara, Takashi*
no journal, ,
In the investigation of measures to enhance safety of a sodium cooled fast reactor, conceptual design of a test apparatus for sodium experiment named AtheNa-RV/DHRS has been conducted at JAEA in corporation with MFBR for feasibility study of the diverse systems for decay heat removal under various operating conditions including the sever accident. Important thermal-hydraulic problems to be studied using AtheNa-RV/DHRS and significant points in the design of it were investigated based on knowledge from the existing investigations regarding decay heat removal systems and results of the preliminary numerical simulation of AtheNa-RV/DHRS in temporal design.
