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impurity band state as the origin of high Curie temperature in the 
-type ferromagnetic semiconductor (Ga,Fe)SbTakeda, Takahito*; Sakamoto, Shoya*; Araki, Kosei*; Fujisawa, Yuita*; Anh, L. D.*; Tu, N. T.*; Takeda, Yukiharu; Fujimori, Shinichi; Fujimori, Atsushi*; Tanaka, Masaaki*; et al.
Physical Review B, 102(24), p.245203_1 - 245203_8, 2020/12
Times Cited Count：7 Percentile：43.4(Materials Science, Multidisciplinary)Kobayashi, Tetsuya; Araki, Masaaki; Oba, Toshinobu; Torii, Yoshiya; Takeuchi, Masaki*
JAEA-Conf 2011-003, p.83 - 86, 2012/03
Araki, Masaaki; Kato, Tomoaki; Arai, Masaji
JAEA-Technology 2010-015, 35 Pages, 2010/06
JAEA-Technology-2010-015.pdf:1.04MB
Research reactor JRR-3 is a light water moderated and cooled pool type research reactor using low enriched uranium-silicon-aluminum-dispersion-type fuel. French Competent Authority (FCA) required that the criticality safety of the JRF-90Y-950K package is maintained even if it is deformed under oblique drops onto a bar. Criticality analyses of the JRF-90Y-950K package were carried out for the transport of JRR-3, JRR-4 or JMTR fuel. The results show that criticality safety is kept even if it is deformed under oblique drops onto a bar.
Kato, Tomoaki; Araki, Masaaki; Izumo, Hironobu; Kinase, Masami; Torii, Yoshiya; Murayama, Yoji
JAEA-Technology 2007-050, 39 Pages, 2007/08
JAEA-Technology-2007-050.pdf:14.09MB
On the conversion from aluminide fuel to silicide fuel, burnable absorbers were introduced for decreasing excess reactivity. The burnable absorbers influence reactivity during reactor operation. So, the burning of the burnable absorbers was studied and the influence on reactor operation was made cleared. Furthermore, necessary excess reactivity on beginning of operation cycle and the time limit for restart after unplanned reactor shutdown was calculated. After the conversion, the fuel exchange procedure was changed from the six-batch dispersion procedure to the fuel burn-up management procedure. The previous estimation of fuel burn-up was required for the planning of fuel exchange, so that the estimation was carried out by means of past operation data. Finally, a new fuel exchange procedure was proposed for effective use of fuel elements. The average length of fuel-staying in the core can be increased by two percent on the procedure.
Kuriyama, Masaaki; ; Araki, Masanori; ; Hanada, Masaya; Inoue, Takashi; Kawai, Mikito; Kazawa, Minoru; *; Kunieda, Shunsuke; et al.
Fusion Engineering and Design, 26, p.445 - 453, 1995/00
Times Cited Count：43 Percentile：95.64(Nuclear Science & Technology)no abstracts in English
Okumura, Yoshikazu; Araki, Masanori; Hanada, Masaya; Inoue, Takashi; Kunieda, Shunsuke; Kuriyama, Masaaki; Matsuoka, Mamoru; Mizuno, Makoto; Ohara, Yoshihiro; Tanaka, Masanobu*; et al.
Production and Neutralization of Negative Ions and Beams; AIP Conference Proceedings 287, p.839 - 848, 1994/00
no abstracts in English
Kuriyama, Masaaki; ; Araki, Masanori; ; Hanada, Masaya; Inoue, Takashi; Kawai, Mikito; Kazawa, Minoru; *; Kunieda, Shunsuke; et al.
15th IEEE/NPSS Symp. on Fusion Engineering,Vol. 1, 0, p.470 - 473, 1993/00
no abstracts in English
Ohara, Yoshihiro; Akiba, Masato; Araki, Masanori; Dairaku, Masayuki; Hanada, Masaya; Inoue, Takashi; Kojima, Hiroaki; Kuriyama, Masaaki; *; Matsuoka, Mamoru; et al.
JAERI-M 90-154, 119 Pages, 1990/09
no abstracts in English
Araki, Masanori; Dairaku, Masayuki; Inoue, Takashi; Komata, Masao; Kuriyama, Masaaki; Matsuda, Shinzaburo; Ogawa, Masuro; Ohara, Yoshihiro; Seki, Masahiro;
Fusion Engineering and Design, 9, p.231 - 236, 1989/00
no abstracts in English
Kuriyama, Masaaki; Araki, Masanori; Horiike, Hiroshi; Matsuda, Shinzaburo; Matsuoka, Mamoru; Ohara, Yoshihiro; Okumura, Yoshikazu; Shibanuma, Kiyoshi; Shirakata, Hirofumi; Tanaka, Shigeru
Fusion Engineering and Design, 9, p.237 - 243, 1989/00
no abstracts in English
Kuriyama, Masaaki; Akiba, Masato; ; Araki, Masanori; Dairaku, Masayuki; ; Horiike, Hiroshi; Ito, Takao; Inoue, Takashi; Kawai, Mikito; et al.
JAERI-M 87-169, 182 Pages, 1987/10
no abstracts in English
Matsuda, Shinzaburo; Akiba, Masato; Araki, Masanori; Dairaku, Masayuki; ; Horiike, Hiroshi; Ito, Takao; *; Kawai, Mikito; Komata, Masao; et al.
Fusion Engineering and Design, 5, p.85 - 100, 1987/00
Times Cited Count：23 Percentile：87.78(Nuclear Science & Technology)no abstracts in English
Araki, Masaaki; Kobayashi, Tetsuya; Oba, Toshinobu; Takeuchi, Masaki
no journal, ,
no abstracts in English
Kimura, Kazuya; Araki, Masaaki; Nagadomi, Hideki; Wada, Shigeru
no journal, ,
no abstracts in English
Iwaasa, Masahiro; Hosoya, Toshiaki; Araki, Masaaki
no journal, ,
no abstracts in English
Kikuchi, Masanobu; Kawamura, Sho; Araki, Masaaki
no journal, ,
We carried out seismic evaluation and showed suitability in the new regulatory standard of JRR-3. CRDM and insertion property of control rod carried out more detailed approach because the past results had gotten the serious results of seismic safety margin. As a result, it was confirmed that CRDM and insertion property of control rod have sufficient seismic safety margin.
Iguchi, Shintaro; Horiguchi, Hironori; Araki, Masaaki
no journal, ,
The intervention level on the practical use by which the principle measurement which are the spatial radiation dose rate and the density of the radioactive materials in the environment sample, etc. as the standard by which implementation of protective measure is judged is expressed in the possible price (OIL) is established by the atomic disaster countermeasures guideline an atomic regulatory committee set. The dose evaluation when changing the fuel damaged percentage conservatively about over the design basic accident of JRR-3 and the reactor core way way blockade accident, was put into effect and OIL1 and OIL2 were compared with the implementation standard of the protective measure by this publication. Just after flow pass of a fuel element was blocked up, radioactive materials are damaged, and are released from fuel to a cooling system, and an evaluation phenomenon and a done reactor core way way blockade accident are the accident released from exhaust equipment for emergency use to ambient surroundings via a shift to a nuclear reactor pool and a building. It didn't operate with the case when exhaust equipment for emergency use normally operated by evaluation, and the occasion which did the ground release was assumed. The dose rate by the nuclide released in the atmosphere from a nuclear reactor building and the dose rate by the nuclide floating in the nuclear reactor building were estimated about dose evaluation. The evaluation point was made a distance 329m spot from JRR-3 to the atomic scientific research place site boundary. It was confirmed that there are also no dose rates beyond the initialization value of OIL1 in the result and just after accident. It was confirmed that the dose rate falls and falls below the initialization value of OIL2 after 6 time course rapidly after an accident.
