Zobrazeno 1 - 10
of 14
pro vyhledávání: '"Hiroki Hayafune"'
Publikováno v:
Journal of the Atomic Energy Society of Japan. 61:798-803
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9e439ca5efbd3a2869c8ac3bc3388564
https://doi.org/10.3327/jaesjb.61.11_798
https://doi.org/10.3327/jaesjb.61.11_798
Publikováno v:
Nuclear Engineering and Design. 324:35-44
An economic calculation model based on detailed mass-flow (hereinafter referred to as the “JAEA model”) was developed for the comprehensive evaluation of an advanced loop-type sodium-cooled fast reactor (SFR) cycle system designed in the Fast Rea
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c696d9f1cdabc9e2675d199f83e37827
https://doi.org/10.1016/j.nucengdes.2017.08.011
https://doi.org/10.1016/j.nucengdes.2017.08.011
Publikováno v:
Nuclear Engineering and Design. 280:586-597
To improve the economic competitiveness of the Japan Sodium-cooled Fast Reactor (JSFR), several innovative designs have been introduced, e.g. reduction of number of main cooling loop, shorter pipe arrangement by adopting thermally durable material, i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c6a0635bc948678c10b24fe6c45be5e5
https://doi.org/10.1016/j.nucengdes.2014.08.031
https://doi.org/10.1016/j.nucengdes.2014.08.031
Autor:
Yoshitaka Chikazawa, Patrick Mariteau, Jean François Sauvage, Gérard Prele, Mari Marianne Uematsu, Hiroki Hayafune
Publikováno v:
Journal of Nuclear Science and Technology. 52:434-447
A comparison of the Japan sodium-cooled fast reactor (JSFR) design with the future French sodium-cooled fast reactor (SFR) concept has been done based on the requirements of Electricite de France (...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::213d20ad57ed1e084d213dd79017e686
https://doi.org/10.1080/00223131.2014.953015
https://doi.org/10.1080/00223131.2014.953015
Publikováno v:
Nuclear Technology. 182:170-186
The Commissariat a L’Energie Atomique et aux Energies Alternatives (CEA) and the Japan Atomic Energy Agency (JAEA) intend to develop prototype or demonstration sodium-cooled fa...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::52df9d07872f93986d261a2d17ad1051
https://doi.org/10.13182/nt13-a16429
https://doi.org/10.13182/nt13-a16429
Autor:
Yushi Ohno, Hiroki Hayafune, Shoji Kotake, Kazumi Aoto, Yoshitaka Chikazawa, Takaya Ito, Mikio Toda
Publikováno v:
Nuclear Technology. 179:360-373
Key technologies for Japan Sodium-cooled Fast Reactor (JSFR) have been evaluated. The ten technologies - high-burnup core, safety enhancement, compact reactor vessel, two-loop cooling system using ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9ab1ea432b582e550a3be377b0994783
https://doi.org/10.13182/nt179-360
https://doi.org/10.13182/nt179-360
Autor:
Kuniyuki Shimoji, Hiroki Hayafune, Iwao Matsumoto, Kazuyoshi Miyagawa, Y. Oda, Takuya Handa, Tomoyuki Inoue, Hiroyasu Ishikawa, Yukihiko Ono
Publikováno v:
Journal of Nuclear Science and Technology. 48:669-676
This paper illuminates the status of research and development on the integrated IHX/Pump concept. The integrated IHX/Pump is the incorporated component of the intermediate heat exchanger (IHX) and the primary pump. Among the innovative technologies o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b8d70822bfe914364c3ea6fe90dc355e
https://doi.org/10.1080/18811248.2011.9711748
https://doi.org/10.1080/18811248.2011.9711748
Autor:
Wei Liu, Kazuyuki Takase, Naoyuki Kisohara, Hiroki Hayafune, Satoshi Futagami, Tamai Hidesada
Publikováno v:
Journal of Power and Energy Systems. 5:229-240
For a steam generator with straight double-walled heat transfer tubes that will be used in a sodium cooled faster breeder reactor, clarification of flow instability in heat transfer tubes is one of the most important research themes. As the first ste
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5a00067f76673a50de2c3219fd2d70dc
https://doi.org/10.1299/jpes.5.229
https://doi.org/10.1299/jpes.5.229
Publikováno v:
Progress in Nuclear Energy. 37:283-290
A way of development to standardize a small fast nuclear reactor system, which is considered one of the suitable concepts at next generation for satisfying such needs as generality, small dependence on natural resources, safety and non-proliferation,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e8ed75a732c5e011dae47d035873b7e5
https://doi.org/10.1016/s0149-1970(00)00060-3
https://doi.org/10.1016/s0149-1970(00)00060-3
Autor:
Satoshi Futagami, Naoyuki Kisohara, Kazuyuki Takase, Wei Liu, Tamai Hidesada, Hiroki Hayafune
Publikováno v:
18th International Conference on Nuclear Engineering: Volume 4, Parts A and B.
For steam generator with straight double-walled heat transfer tube that used in sodium cooled Faster Breeder Reactor, flow instability is one of the most important items need researching. As the first step of the research, thermal hydraulics experime
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::88b1c713ae03664b5750fe360506c2aa
https://doi.org/10.1115/icone18-30167
https://doi.org/10.1115/icone18-30167