Zobrazeno 1 - 10
of 68
pro vyhledávání: '"Hidetoshi Okada"'
Autor:
Toyohiko Honda, Kazuma Ikeda, Kazuo Tsubaki, Masao Kobayashi, Mayumi Matsumoto, Marie Tagashira, Hidetoshi Okada, Shiho Makino
Publikováno v:
Japanese Journal of Transfusion and Cell Therapy. 66:559-565
Publikováno v:
SSRN Electronic Journal.
Autor:
Masanori Naitoh, Hiroshige Kikura, Shunsuke Uchida, Masayoshi Kojima, Hidetoshi Okada, Derek H. Liste
Publikováno v:
Nuclear Engineering and Design. 337:84-95
Improvement of plant reliability based on reliability-centered-maintenance (RCM) is going to be undertaken in nuclear power plants (NPPs). RCM is supported by three types of maintenances: risk-based maintenance (RBM); time-based maintenance (TBM); an
Publikováno v:
Corrosion Engineering, Science and Technology. 52:587-595
A model to evaluate the electrochemical corrosion potential (ECP) and corrosion rate of stainless steel in neutral water was developed by coupling a static electrochemical analysis and a dynamic oxide layer growth analysis. ECP is much affected not o
Autor:
Takuma Sadamori, Hidetoshi Okada, Masao Kobayashi, Kazuo Tsubaki, Hirochika Odawara, Kazuhiro Hosokawa, Fumikazu Murakami
Publikováno v:
Japanese Journal of Transfusion and Cell Therapy. 66:1-2
Autor:
Hiroshige Kikura, Y. Chimi, Masanori Naitoh, Masayoshi Kojima, Shigeki Kasahara, Derek H. Lister, Satoshi Hanawa, Hidetoshi Okada, Shunsuke Uchida
Publikováno v:
Nuclear Engineering and Design.
Improvement of plant reliability based on reliability-centred maintenance (RCM) is going to be implemented in nuclear power plants. RCM is supported by three types of maintenances: risk-based maintenance (RBM); time-based maintenance; and condition-b
Autor:
Hiroyuki Suzuki, Masahiro Fujikawa, Ayumi Itoh, Hidetoshi Okada, Masahiro Osakabe, Masanori Naitoh, Yukio Hanamoto, Shunsuke Uchida
Publikováno v:
Nuclear Engineering and Design. 298:201-207
The wet-well of boiling water reactors plays important roles not only to suppress the pressure in the primary containment vessel due to steam scrubbing effects during severe accidents but also to mitigate release of radioactive fission products (FP),
Autor:
Shinya Mizokami, Jun Sugimoto, Shoichi Suehiro, Hidetoshi Okada, Koji Okamoto, Akihide Hidaka
Publikováno v:
Nuclear Engineering and Design. 286:163-174
Research Expert Committee on Evaluation of Severe Accident of AESJ (Atomic Energy Society of Japan) has developed thermal hydraulic PIRT (Phenomena Identification and Ranking Table) and source term (ST) PIRT based on findings during the Fukushima Dai
Publikováno v:
Nuclear Technology. 188:252-265
As a result of the mass balance analysis for fission products (FPs) in the contaminated water accumulated in the Fukushima Daiichi nuclear power plant in the aftermath of the accident, it was concl...
Publikováno v:
Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events.
In view of the 1F decommissioning project, the Institute of Applied Energy (IAE) has been analyzing the course of the accident using the SAMPSON code with an aim to investigate its progression in detail. For 1F Unit-2, certain discrepancies between m