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Ishizawa, Akihiro*; Idomura, Yasuhiro; Imadera, Kenji*; Kasuya, Naohiro*; Kanno, Ryutaro*; Satake, Shinsuke*; Tatsuno, Tomoya*; Nakata, Motoki*; Nunami, Masanori*; Maeyama, Shinya*; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 92(3), p.157 - 210, 2016/03
The high-performance computer system Helios which is located at The Computational Simulation Centre (CSC) in The International Fusion Energy Research Centre (IFERC) started its operation in January 2012 under the Broader Approach (BA) agreement between Japan and the EU. The Helios system has been used for magnetised fusion related simulation studies in the EU and Japan and has kept high average usage rate. As a result, the Helios system has contributed to many research products in a wide range of research areas from core plasma physics to reactor material and reactor engineering. This project review gives a short catalogue of domestic simulation research projects. First, we outline the IFERC-CSC project. After that, shown are objectives of the research projects, numerical schemes used in simulation codes, obtained results and necessary computations in future.
Yashiro, Shigeo; Aoki, Kazuhisa; Sato, Tomohiko; Tanji, Kazuhiro
JAEA-Review 2013-038, 123 Pages, 2014/01
JAEA-Review-2013-038.pdf:23.19MB
With the rapid progress of the utilization of Information Technology (IT), IT infrastructure (network environment and information system) became crucial as a lifeline for promoting business. At the same time, changes in the circumstances surrounding the IT infrastructure globalize the threat of cyber attacks and increase the risk of the information security such as unlawful access to an information system, viral infection, an alteration of a website, disclosure of subtlety information, destruction of an information system and so on. Information security measure is an important issue in Japan Atomic Energy Agency (JAEA). In order to protect the information property of JAEA from the threat, Center for Computational Science & e-Systems (CCSE) has been taking triadic measures for information security: (1) to lay down a set of information security rules, (2) to introduce security equipments to backbone network and (3) to provide information security education. This report is a summary of the contents of the information security education by e-learning.
Hirayama, Takashi; Kannari, Masaaki; Sato, Tomohiko
JAEA-Testing 2012-002, 29 Pages, 2012/06
JAEA-Testing-2012-002.pdf:2.98MB
In pursuance of "The Optimization Plan on the network of JAEA", which aims to ensure network reliability and information security and to improve convenience in using the network, we are engaged in the optimization of inter-institute/center network bandwidth. This is a record of an introduction of WAN accelerator into the network to Ningyo-toge Environmental Engineering Center which bandwidth is limited due to a geographically constraint.
Hirano, Fumio; Sato, Seichi*; Kozaki, Tamotsu*; Inagaki, Yaohiro*; Iwasaki, Tomohiko*; Oe, Toshiaki*; Kato, Kazuyuki*; Kitayama, Kazumi*; Nagasaki, Shinya*; Niibori, Yuichi*
Journal of Nuclear Science and Technology, 49(3), p.310 - 319, 2012/03
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)The thermal impacts of hull and end piece wastes from the reprocessing of MOX spent fuels burned in LWRs on repository performance were investigated. The heat generation rates in MOX spent fuels and the resulting heat generation rates in hull and end piece wastes change depending on the fuel histories including the burn-up of UO
spent fuels, the cooling period before reprocessing, the storage period of fresh MOX fuels. The heat generation rates of hull and end piece wastes from the reprocessing of MOX spent fuels with any of those histories are significantly larger than those from UO spent fuels with burn-ups of 45 GWd/THM. If a temperature below 80
C is specified for cement-based materials used in waste packages after disposal, the allowable number of canisters containing compacted hull and end pieces in a package for 45 GWd-MOX needs to be limited to a value of 0.7 to 1.6, which is significantly lower than the value of 4.0 for 45 GWd-UO.
Nishitani, Takeo; Okada, Koichi; Sato, Satoshi; Sasao, Mamiko*; Iwasaki, Tomohiko*; Sugawara, Takanori; Shinto, Katsuhiro*; Kitajima, Sumio*; Nomura, Ken*
no journal, ,
no abstracts in English
Okada, Koichi; Kondo, Keitaro; Sato, Satoshi; Nishitani, Takeo; Nomura, Ken*; Okamoto, Atsushi*; Iwasaki, Tomohiko*; Kitajima, Sumio*; Sasao, Mamiko*
no journal, ,
no abstracts in English
Sato, Ikken; Iwasaki, Tomohiko*; Konashi, Kenji*
no journal, ,
no abstracts in English
Sato, Ikken; Iwasaki, Tomohiko*; Konashi, Kenji*
no journal, ,
Concerning safety characteristics of FBR core with hydride control materials, representative accidents for design basis and those beyond the design basis were selected and transient responses were evaluated. Based on this result, it was concluded that no unfavorable response was expected for this option.
Pirozhkov, A. S.; Kando, Masaki; Esirkepov, T. Z.; Pikuz, T.; Faenov, A. Ya.*; Ogura, Koichi; Hayashi, Yukio; Kotaki, Hideyuki; Ragozin, E. N.*; Neely, D.*; et al.
no journal, ,
Pirozhkov, A. S.; Kando, Masaki; Esirkepov, T. Z.; Pikuz, T.; Faenov, A. Ya.*; Ogura, Koichi; Hayashi, Yukio; Kotaki, Hideyuki; Ragozin, E. N.*; Neely, D.*; et al.
no journal, ,
Pirozhkov, A. S.; Kando, Masaki; Esirkepov, T. Z.; Pikuz, T.; Faenov, A. Ya.*; Ogura, Koichi; Hayashi, Yukio; Kotaki, Hideyuki; Ragozin, E. N.*; Neely, D.*; et al.
no journal, ,
Sato, Hisaki*; Kakiuchi, Kazuo*; Ishibashi, Ryo*; Ikegawa, Tomohiko*; Kondo, Takao*; Yamashita, Shinichiro; Fukahori, Tokio
no journal, ,
SiC composite materials applied to a cladding tube and a channel box for BWR have been developed for introduction of the accident tolerant fuel to an existing LWRs. The outline of the outcome in fiscal year 2017 will be introduced by this presentation.
Okazaki, Kodai*; Kawakami, Tomohiko*; Abe, Yuta; Otaka, Masahiko; Sato, Ikken
no journal, ,
no abstracts in English
