Zobrazeno 1 - 10
of 17
pro vyhledávání: '"Hiroshi Sakaba"'
Autor:
Hiroshi Sakaba
Publikováno v:
Journal of the Atomic Energy Society of Japan. 64:200-202
Autor:
Hiroyuki Hara, Yoshio Shimakawa, Mikinori Iwasaki, Yoshitaka Chikazawa, Tomohiko Yamamoto, Shuji Ohno, Hiroshi Sakaba, Atsushi Katoh, Shigenobu Kubo
Publikováno v:
Nuclear Technology. 196:61-73
The Japan Sodium-cooled Fast Reactor (JSFR) adopts a double boundary for all sodium components. In this paper, design measures are investigated against a secondary sodium fire inside the reactor building, which might be assumed as design extension co
Autor:
Mamoru Numata, Tetsushi Hino, Masao Chaki, Hiroki Takimoto, Hiroshi Sakaba, Masayoshi Matsuura, Takayuki Amaya, Kumiaki Moriya, Kouki Hibi
Publikováno v:
Transactions of the Atomic Energy Society of Japan. 5:257-267
Autor:
Naoki Yoshioka, Michael Epstein, Masanori Tashimo, Shoji Kotake, Hans K. Fauske, Hiroshi Sakaba
Publikováno v:
Journal of Nuclear Science and Technology. 43:43-54
A model for predicting the peak temperature within an oxidizer-steam jet submerged in molten sodium is described. Previous experimental and theoretical work by the present authors has shown that a single, representative droplet size may be used to mo
Autor:
Michael Epstein, Naoki Yoshioka, Hans K. Fauske, Masanori Tashimo, Hiroshi Sakaba, Shoji Kotake
Publikováno v:
Journal of Nuclear Science and Technology. 42:949-960
In order to establish an analytical model for the peak temperature within a sodium-water reaction jet, an analytical and theoretical investigation of an inert-hot-gas jet injected into a bath of cold liquid was performed as the first step. The labora
Autor:
Kazuya Koyama, Akiko Kaneko, Ken-ichi Ebihara, Kazuhiro Itoh, Eiji Matsuo, Yuzuru Iwasawa, Shimpei Saito, Hideki Nariai, Hiroshi Sakaba, Yutaka Abe
Publikováno v:
Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events.
For the safety design of a Fast Breeder Reactor (FBR), if a Core Disruptive Accident (CDA) occurred hypothetically, it is required to suppress the rapid energy release due to a prompt criticality. Even if the rapid energy release does not occur, ther
Autor:
Eiji Matsuo, Yuzuru Iwasawa, Hiroshi Sakaba, Shimpei Saito, Hideki Nariai, Ken-ichi Ebihara, Akiko Kaneko, Kazuya Koyama, Yutaka Abe
Publikováno v:
Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition.
Mitigative measures against a Core Disruptive Accident (CDA) are important from the viewpoints of safety of a Fast Breeder Reactor (FBR). If a CDA occurs, Post Accident Heat Removal (PAHR) must be surely achieved. In the PAHR, molten materials are li
Autor:
Taihei Kuroda, Kazuya Koyama, Ken-ichi Ebihara, Yutaka Abe, Kazuhiro Itoh, Eiji Matsuo, Yuzuru Iwasawa, Hideki Nariai, Hiroshi Sakaba, Akiko Kaneko
Publikováno v:
Volume 6: Beyond Design Basis Events; Student Paper Competition.
For the safety design of a Fast Breeder Reactor (FBR), Post Accident Heat Removal (PAHR) is required when a hypothetical Core Disruptive Accident (CDA) occurs. In PAHR, it is strongly required that the molten core material can be solidified and coole
Autor:
Akiko Kaneko, Hideki Nariai, Eiji Matsuo, Yutaka Abe, Taihei Kuroda, Yuzuru Iwasawa, Hiroshi Sakaba, Kazuya Koyama, Kazuhiro Itoh
Publikováno v:
Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles.
When a hypothetical Core Disruptive Accident (CDA) occurs in Fast Breeder Reactor (FBR), it is strongly required that the molten core material can be solidified and cooled down by the sodium coolant in a reactor vessel. In order to estimate whether t
Autor:
Ken-ichi Ebihara, Kazuya Koyama, Tetsuya Kanagawa, Yutaka Abe, Yuzuru Iwasawa, Hiroshi Sakaba, Hideki Nariai, Shimpei Saito, Akiko Kaneko, Eiji Matsuo
Publikováno v:
The Proceedings of the International Conference on Nuclear Engineering (ICONE). :ICONE23-1