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Takahashi, Naoki; Suzuki, Soju; Saito, Hiroto; Ueno, Takashi; Abe, Sadayoshi; Yamanaka, Atsushi; Tanigawa, Masafumi; Nakamura, Daishi; Sasaki, Shunichi; Mine, Tadaharu
Nihon Genshiryoku Gakkai Homu Peji (Internet), 20 Pages, 2017/05
no abstracts in English
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.
Yoshinaka, Kazuyuki; Abe, Sadayoshi
Gijutsushi, 27(6), p.4 - 7, 2015/06
In a reprocessing plant, some apparatuses are in severe corrosive condition, like exposure to boiling nitric acid. Safety functions, like fire prevention on organic solvent, are needed on some apparatuses. To maintain the apparatuses and functions, various inspections are performed. The features of the maintenance in high dose, are represented in experiences of remote operation. The way of decommissioning of Tokai Reprocessing Plant has been indicated last year. But importance of maintenance will not change, because the apparatuses for treatment of high level liquid waste will be used for long term. Continuing development of remote maintenance technology and contribution to decommissioning Fukushima Dai-ichi NPP are expected.
Abe, Sadayoshi
Kokyosei No Takai Shisetsu No Iji Kanri, p.110 - 115, 2014/10
I will explain the fact of aging and anti-maintenance Nuclear Fuel Cycle Facilities in (Reprocessing Facility).
Abe, Sadayoshi
Genshiryoku, Hoshasen No Seiri To Kento No Tameno Shiryo; 3.11 Fukushima Daiichi Genshiryoku Hatsudensho Jiko Ni Tsuite Tomoni Kangaeru, p.101 - 102, 2013/03
In Tomioka town, Fukushima Prefecture, we revealed the social contribution made through the assistance observer was designed for "Disaster Recovery Planning Commission" and "vision development committee earthquake reconstruction."
Abe, Sadayoshi
Gijutsushi, 25(1), p.28 - 29, 2013/01
We revealed been organized in Tomioka town, Fukushima Prefecture, to contribute to society through support of the planning committee and development committee vision disaster reconstruction.
Abe, Sadayoshi
Fuji Sankei Business i, (20147), 1 Pages, 2012/11
Disaster reconstruction in vision development committee in Tomioka town, Fukushima Prefecture, supplemented with radiation, making the reconstruction plan of the town feel.
Abe, Sadayoshi; Kuwae, Yoshiaki*; Sasaki, Satoru*; Takahashi, Kazutoshi*
Genshiryoku, hoshasen Bukaiho (Internet), (10), p.6 - 8, 2012/03
Between January 30, 2012 August 26, 2011, the support for the correct understanding of nuclear and radiation due to comments and advice to participate in disaster reconstruction committee formulated vision of the Tomioka town, as a professional Engineers, Japan was carried out, As a result, the vision I hope to go back to town Tomioka are taken together to form all townspeople have been developed.
Kurihara, Ryoichi; Nakano, Junichi; Abe, Sadayoshi
Genshiryoku eye, 57(3), p.71 - 76, 2011/03
no abstracts in English
Isayama, Akihiko; Sakakibara, Satoru*; Furukawa, Masaru*; Matsunaga, Go; Yamazaki, Kozo*; Watanabe, Kiyomasa*; Idomura, Yasuhiro; Sakamoto, Yoshiteru; Tanaka, Kenji*; Tamura, Naoki*; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 86(6), p.374 - 377, 2010/06
no abstracts in English
Nakano, Tomohito*; Abe, Sadayoshi
Genshiryoku eye, 56(2), p.72 - 76, 2010/02
This case, the primary examiner in 2009 subjects Years of Professional Engineers (Department of Atomic Radiation) overview of, and a description of the energy sector.
Nakano, Tomohito*; Mizutani, Akira*; Abe, Sadayoshi; Tomida, Kazuo*; Handa, Hiroyuki*
Genshiryoku eye, 56(1), p.63 - 76, 2010/01
no abstracts in English
Osakabe, Masaki*; Shinohara, Koji; Toi, Kazuo*; Todo, Yasushi*; Hamamatsu, Kiyotaka; Murakami, Sadayoshi*; Yamamoto, Satoshi*; Idomura, Yasuhiro; Sakamoto, Yoshiteru; Tanaka, Kenji*; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 85(12), p.839 - 842, 2009/12
no abstracts in English
Idomura, Yasuhiro; Yoshida, Maiko; Yagi, Masatoshi*; Tanaka, Kenji*; Hayashi, Nobuhiko; Sakamoto, Yoshiteru; Tamura, Naoki*; Oyama, Naoyuki; Urano, Hajime; Aiba, Nobuyuki; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 84(12), p.952 - 955, 2008/12
no abstracts in English
Motojima, Osamu*; Yamada, Hiroshi*; Komori, Akio*; Oyabu, Nobuyoshi*; Muto, Takashi*; Kaneko, Osamu*; Kawahata, Kazuo*; Mito, Toshiyuki*; Ida, Katsumi*; Imagawa, Shinsaku*; et al.
Nuclear Fusion, 47(10), p.S668 - S676, 2007/10
Times Cited Count：35 Percentile：73.49(Physics, Fluids & Plasmas)The performance of net-current free heliotron plasmas has been developed by findings of innovative operational scenarios in conjunction with an upgrade of the heating power and the pumping/fuelling capability in the Large Helical Device (LHD). Consequently, the operational regime has been extended, in particular, with regard to high density, long pulse length and high beta. Diversified studies in LHD have elucidated the advantages of net-current free heliotron plasmas. In particular, an internal diffusion barrier (IDB) by a combination of efficient pumping of the local island divertor function and core fuelling by pellet injection has realized a super dense core as high as 5
10
m
, which stimulates an attractive super dense core reactor. Achievements of a volume averaged beta of 4.5% and a discharge duration of 54 min with a total input energy of 1.6 GJ (490 kW on average) are also highlighted. The progress of LHD experiments in these two years is overviewed by highlighting IDB, high-beta and long pulse.
Motojima, Osamu*; Yamada, Hiroshi*; Komori, Akio*; Oyabu, Nobuyoshi*; Kaneko, Osamu*; Kawahata, Kazuo*; Mito, Toshiyuki*; Muto, Takashi*; Ida, Katsumi*; Imagawa, Shinsaku*; et al.
Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 12 Pages, 2007/03
The performance of net-current free Heliotron plasmas has been developed by findings of innovative operational scenarios in conjunction with an upgrade of the heating power and the pumping/fueling capability in the Large Helical Device (LHD). Consequently, the operational regime has been extended, in particular, with regard to high density, long pulse length and high beta. Diversified studies in LHD have elucidated the advantages of net-current free heliotron plasmas. In particular, an Internal Diffusion Barrier (IDB) by combination of efficient pumping of the local island divertor function and core fueling by pellet injection has realized a super dense core as high as 510m, which stimulates an attractive super dense core reactor. Achievements of a volume averaged beta of 4.5 % and a discharge duration of 54-min. with a total input energy of 1.6 GJ (490 kW in average) are also highlighted. The progress of LHD experiments in these two years is overviewed with highlighting IDB, high 
and long pulse.
Ida, Katsumi*; Fujita, Takaaki; Fukuda, Takeshi*; Sakamoto, Yoshiteru; Ide, Shunsuke; Toi, Kazuo*; Inagaki, Shigeru*; Shimozuma, Takashi*; Kubo, Shin*; Idei, Hiroshi*; et al.
Plasma Physics and Controlled Fusion, 46(5A), p.A45 - A50, 2004/05
Times Cited Count：19 Percentile：52.13(Physics, Fluids & Plasmas)no abstracts in English
; Abe, Sadayoshi*; Iguchi, Tatsuro*
PNC TN941 84-69, 39 Pages, 1984/04
The flow induced vibration of a fuel pin bundle is considered to be one of the major factors causing wear marks observed on "JOYO" MK-I fuel claddings. This experiment was performed by using a fuel pin bundle having porosity/ring of twice as large as that of "JOYO" MK-I fuel assembly, in order to study the effect of porosity/ring on the flow induced vibration of pins. The following was clarified from the comparison between the results of this experiment and the previous one using the test bundle of porosity/ring equal to that of "JOYO" MK-I fuel assembly. Any significant fuel pin vibration was not observed in the deformed bundle test in which the deformed pins were lined up on the outermost row simulating thermal bowing of the fuel assembly irradiated in reactor, because the restrain effect of the deformed peripheral pins was larger than that of porosity/ring. The similar result ,had been obtained in the previous experiment. In the test of normal bundle without any deformed pin, the fuel pin vibration was much larger in this experiment than the previous one. This experimental result showed that the effect of porosity/ring on the vibration was significant in the normal bundle.
Abe, Sadayoshi*; ; Iguchi, Tatsuro*
PNC TN941 84-67, 30 Pages, 1984/04
The objective of this experimental study is to obtain the data on pressure loss characteristics of the fuel assembly which must be deformed during hypothetical core disruptive accident (HCDA). Three of deformed bundle and one of normal shaped bundle were used in the experiment. These bundles had the same geometry as the fuel bundle part of "Monju" blanket assembly. The main conclusions are as follows: The pressure loss (
P) of deformed bundle at the same Reynolds numbers as normal bundle can approximately predicted by using the ratio of cross sectional flow area(A), as shown below. (P(deformed))/((normal)) = (A(normal)/A(deformed))
. This equation is applicable with the following limitations. (1)Reynolds numbers defined at bundle area is 10
to 310
. (2)Reduction of flow area is within 17% of flow area of normal bundle. Prediction area of the equation is less than 8% and 3% for the range of Reynolds number of 10 to 810 and 810 to 310, respectively.
