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Journal Articles

Plant system study of France-Japan common concept on Sodium-cooled Fast Reactor

Kato, Atsushi; Yamamoto, Tomohiko; Ando, Masato; Chikazawa, Yoshitaka; Murakami, Hisatomo*; Oyama, Kazuhiro*; Kaneko, Fumiaki*; Higurashi, Koichi*; Chanteclair, F.*; Chenaud, M.-S.*; et al.

EPJ Nuclear Sciences & Technologies (Internet), 8, p.11_1 - 11_10, 2022/06

This paper provides an overview of plant system studies to establish a common technical view for Sodium-cooled Fast Reactor concept between France and Japan based on ASTRID600 and the new concept with downsized output called ASTRID150. One of important issues on a reactor structure design is to enhance seismic resistance to be tolerable against strong earthquake such that postulated in Japan. A concept of High Frequency Design is shared, and the design options related to HFD have been examined and design recommendations are established. In addition, this paper include results of studies for a steam generator, a decay heat removal system, a fuel handling system and a containment vessel.

Journal Articles

Design study on measures to prevent loss of decay heat removal in a next generation sodium-cooled fast reactor

Chikazawa, Yoshitaka; Kubo, Shigenobu; Shimakawa, Yoshio*; Kaneko, Fumiaki*; Shoji, Takashi*; Nakata, Shuhei*

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 7 Pages, 2017/04

Sodium-cooled reactor (SFR) has superior characteristics thanks to sodium coolant features such as low pressure and high natural convection capability. Involving lessons learned from the 1F accident, requirements on design base DHRS have been modified. In that modification, safety requirements on design extended conditions have been clarified and sodium temperature criteria have been changed taking into account design margin even for design extended conditions. With the new DHRS configuration including ACS, designs of component cooling water system and emergency power supply have been updated.

Journal Articles

Generation method of underwater landmarks for ocean observation

Takahashi, Satoru*; Nota, Yoshiki*; Matsuda, Asahi*; Kawabata, Kuniaki; Suzuki, Tsuyoshi*; Takemura, Fumiaki*; Ogasawara, Kei*; Kaneko, Shunichi*

Journal of Signal Processing, 21(1), p.15 - 24, 2017/01

In recent years, many researchers try to observe the state of the global environment from marine information for the understanding of the global environment change. First, we introduce the recording system of underwater environment which is made by the authors. By using this system, we want to observe the change of global environment from the coral bleaching. In this paper, especially, we propose the generation method of underwater landmark which is used to measure the position of robot of oceanographic observation based on the dynamic image processing. In here, underwater landmark means the feature point in underwater image.

Journal Articles

Evaluation of external event effects on JSFR fuel handling system

Kato, Atsushi; Chikazawa, Yoshitaka; Uzawa, Masayuki*; Kaneko, Fumiaki*; Ide, Akihiro*

Nuclear Technology, 189(1), p.30 - 44, 2015/01

 Times Cited Count:1 Percentile:9.74(Nuclear Science & Technology)

Responding to the Fukushima Dai-ichi Nuclear Power Plant (1F-NPP) accident, robustness of the fuel handling system (FHS) in Japan sodium-cooled fast reactor (JSFR) against the earthquake and the tsunami is studied for 2010 design version. In the earthquake estimation, the margin of seismic resistance and the sloshing in Ex-vessel fuel storage tank (EVST) against the earthquake of the 1F-envelop condition was estimated. In terms of the tsunami evaluation, the scenario to lead fuel subassemblies into the stable cooling state and the potential of the cooling system are introduced in case of the loss of emergency power supply. As a result, it showed that JSFR FHS in the original design already had the potential to prevent the release of radioactive material. Additionally, some design improvements of the EVST cooling system was introduced.

Journal Articles

Progress of design study on fuel handling system in JSFR against design extension conditions

Otaka, Masahiko; Kato, Atsushi; Chikazawa, Yoshitaka; Uzawa, Masayuki*; Ide, Akihiro*; Kaneko, Fumiaki*; Hara, Hiroyuki*

Proceedings of 2014 International Congress on the Advances in Nuclear Power Plants (ICAPP 2014) (CD-ROM), p.607 - 615, 2014/04

Responding to the TEPCO's Fukushima Dai-ichi Nuclear Power Station accident, the design study was carried out to enhance cooling function of fuel handling system for Japan sodium-cooled fast reactor (JSFR). Design measures to maintain an FHS cooling function even in case of Design Extension Conditions are studied; such as alternative cooling systems which are independent and diversified from design basis cooling systems. Based on effectiveness evaluations, it was confirmed that these measures have adequate availability against the postulated design extension conditions.

Journal Articles

A Proton accelerator for neutron science project at JAERI

Mizumoto, Motoharu; Kusano, Joichi; Hasegawa, Kazuo; Ouchi, Nobuo; Oguri, Hidetomo; Kinsho, Michikazu; Chishiro, Etsuji*; Tomisawa, Tetsuo; Touchi, Y.*; Honda, Yoichiro*; et al.

Proc. of 1st Asian Particle Accelerator Conf. (APAC98), p.309 - 313, 1998/11

no abstracts in English

Journal Articles

High intensity proton accelerator for neutron science project at JAERI

Akaoka, Nobuo*; Chishiro, Etsuji*; Hasegawa, Kazuo; Honda, Yoichiro*; Ino, H.*; Kaneko, H.*; Kinsho, Michikazu; Kusano, Joichi; Mizumoto, Motoharu; Mukugi, Ken*; et al.

Proceedings of 6th European Particle Accelerator Conference (EPAC98) (CD-ROM), 2 Pages, 1998/09

no abstracts in English

Journal Articles

A High intensity proton linac development for the JAERI neutron science project

Mizumoto, Motoharu; Kusano, Joichi; Hasegawa, Kazuo; Ouchi, Nobuo; Oguri, Hidetomo; Kinsho, Michikazu; Chishiro, Etsuji*; Tomisawa, Tetsuo; Touchi, Y.*; Ikegami, Masanori*; et al.

Proc. of XIX Int. Linac Conf. (LINAC98), 1, p.349 - 353, 1998/00

no abstracts in English

Journal Articles

Development of high intensity accelerator for neutron science project

Mizumoto, Motoharu; Kusano, Joichi; Hasegawa, Kazuo; Ouchi, Nobuo; Oguri, Hidetomo; Kinsho, Michikazu; Touchi, Y.*; Honda, Yoichiro*; Mukugi, Ken*; Ino, H.*; et al.

Proc. of 11th Symp. on Accelerator Sci. and Technol., p.130 - 132, 1997/00

no abstracts in English

Journal Articles

Development of high intensity proton accelerator

Mizumoto, Motoharu; Kusano, Joichi; Hasegawa, Kazuo; Ouchi, Nobuo; Oguri, Hidetomo; Kinsho, Michikazu; Touchi, Y.*; Honda, Yoichiro*; Mukugi, Ken*; Ino, H.*; et al.

Proc. of Int. Conf. on Future Nuclear Systems (Global'97), 2, p.1402 - 1407, 1997/00

no abstracts in English

Journal Articles

High intensity proton accelerator for neutron science project at JAERI

Kinsho, Michikazu; Mizumoto, Motoharu; Kusano, Joichi; Hasegawa, Kazuo; Ouchi, Nobuo; Oguri, Hidetomo; Touchi, Y.*; Mukugi, Ken*; Ino, H.*; Honda, Yoichiro*; et al.

Topical Meeting on Nuclear Applications of Accelerator Technol., p.85 - 90, 1997/00

no abstracts in English

Oral presentation

Study on countermeasure against design extension conditions for spent fuel storage facilities of JSFR

Otaka, Masahiko; Kato, Atsushi; Chikazawa, Yoshitaka; Ide, Akihiro*; Kaneko, Fumiaki*; Hara, Hiroyuki*; Uzawa, Masayuki*

no journal, , 

Design study was carried out for enhancement of cooling function of fuel storage facilities in Japan Sodium-cooled Fast Reactor (JSFR). Design measures to maintain cooling function even in case of postulated design extension conditions are studied; such as an alternative cooling system for design basis components, multiplying cooling lines, concerning diversity of a cooling ways, etc.

Oral presentation

Study on reliability enhancement of JSFR spent fuel pool facility

Otaka, Masahiko; Kato, Atsushi; Chikazawa, Yoshitaka; Uzawa, Masayuki*; Kaneko, Fumiaki*

no journal, , 

Reliability of JSFR spent fuel pool make-up system was improved through design study including related evaluation on the cooling capability under extreme high ambient temperature conditions.

Oral presentation

Measures for loss of decay heat removal system in the next generation sodium-cooled fast reactor

Chikazawa, Yoshitaka; Kubo, Shigenobu; Shimakawa, Yoshio*; Kaneko, Fumiaki*; Shoji, Takashi*; Nakata, Shuhei*

no journal, , 

Measures against loss of heat removal system (LOHRS) type events in the next generation sodium-cooled reactor (SFR) have been developed. While the next generation SFR already has three-independent decay heat removal systems for design basis. An additional auxiliary cooling system is installed.

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