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and Br and its effect on corrosion of a low-alloy steelHata, Kuniki; Inoue, Hiroyuki*; Kojima, Takao*; Kasahara, Shigeki; Hanawa, Satoshi; Ueno, Fumiyoshi; Tsukada, Takashi; Iwase, Akihiro*
Proceedings of Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia 2017 (AWC 2017) (USB Flash Drive), p.304 - 314, 2017/09
A model simulation of 
radiolysis of mixed solutions of NaCl and NaBr was carried out. The simulation result agreed well with the experimental result, and Br played an important role in determining the amounts of products from water radiolysis. The simulation result also showed that, in highly pure NaCl solutions, the steady-state concentration of a radolytic product, H
O, was mainly controlled by three reactions (Cl + 
OH 
ClOH
, ClOH Cl + OH, and ClOH + H
Cl + HO), which indicated that accurate evaluation of the rate constants of these reactions was very important in improving the radiolysis simulation of solutions containing Cl. An immersion test using a low-alloy steel, SQV2A, in the mixed solutions was also carried out under irradiation. The corrosion rate increased or decreased depending on the pH or the concentrations of the halide ions in a similar way to the change in concentration of HO produced from water radiolysis, which is affected by the presence of Cl and Br. However, at high pH values (
12), the corrosion rate was almost zero even though the concentration of HO was high. This could be attributed to enhancement of the passivity of test specimens at higher pH values.
irradiationYukawa, Takuji*; Inoue, Hiroyuki*; Kojima, Takao*; Iwase, Akihiro*; Taniguchi, Naoki; Tachikawa, Hirokazu*
Zairyo To Kankyo 2016 Koenshu (CD-ROM), p.359 - 362, 2016/05
The immersion tests of pure titanium were carried out in aqueous solution containing carbonate/bicarbonate with 50 mM-chloride ion under gamma irradiation. The effect of pH on general corrosion rate of titanium were studied. The experimental results showed that the concentration of hydrogen preoxide was increased with pH, and the corrosion rate increased with the hydrogen preoxide concentration. The corrosion rate in pH12 and 13 were 5 to10 times larger than those under unirradiated conditions.
radiolysis of sodium chloride solutions containing a small amount of bromide ionHata, Kuniki; Inoue, Hiroyuki*; Kojima, Takao*; Iwase, Akihiro*; Kasahara, Shigeki; Hanawa, Satoshi; Ueno, Fumiyoshi; Tsukada, Takashi
Nuclear Technology, 193(3), p.434 - 443, 2016/03
Times Cited Count：13 Percentile：77.16(Nuclear Science & Technology)
nitridation reactions at metal surfaces by molecular beams and their observation via synchrotron radiation photoemission spectroscopy, 2Teraoka, Yuden; Inoue, Keisuke*; Jinno, Muneaki*; Harries, J.; Okada, Ryuta; Iwai, Yutaro*; Takaoka, Tsuyoshi*; Yoshigoe, Akitaka; Komeda, Tadahiro*
Dai-56-Kai Nihon Gakujutsu Kaigi Zairyo Kogaku Rengo Koenkai Koen Rombunshu, p.360 - 361, 2012/10
no abstracts in English
collisions at 
= 200 and 62.4 GeVAdare, A.*; Afanasiev, S.*; Aidala, C.*; Ajitanand, N. N.*; Akiba, Yasuyuki*; Al-Bataineh, H.*; Alexander, J.*; Aoki, Kazuya*; Aphecetche, L.*; Armendariz, R.*; et al.
Physical Review C, 83(6), p.064903_1 - 064903_29, 2011/06
Times Cited Count：184 Percentile：99.44(Physics, Nuclear)Transverse momentum distributions and yields for 
, and 
in collisions at = 200 and 62.4 GeV at midrapidity are measured by the PHENIX experiment at the RHIC. We present the inverse slope parameter, mean transverse momentum, and yield per unit rapidity at each energy, and compare them to other measurements at different collisions. We also present the scaling properties such as 
and 
scaling and discuss the mechanism of the particle production in collisions. The measured spectra are compared to next-to-leading order perturbative QCD calculations.
Tobita, Kenji; Nishio, Satoshi*; Enoeda, Mikio; Nakamura, Hirofumi; Hayashi, Takumi; Asakura, Nobuyuki; Uto, Hiroyasu; Tanigawa, Hiroyasu; Nishitani, Takeo; Isono, Takaaki; et al.
JAEA-Research 2010-019, 194 Pages, 2010/08
JAEA-Research-2010-019-01.pdf:48.47MBJAEA-Research-2010-019-02.pdf:19.4MB
This report describes the results of the conceptual design study of the SlimCS fusion DEMO reactor aiming at demonstrating fusion power production in a plant scale and allowing to assess the economic prospects of a fusion power plant. The design study has focused on a compact and low aspect ratio tokamak reactor concept with a reduced-sized central solenoid, which is novel compared with previous tokamak reactor concept such as SSTR (Steady State Tokamak Reactor). The reactor has the main parameters of a major radius of 5.5 m, aspect ratio of 2.6, elongation of 2.0, normalized beta of 4.3, fusion out put of 2.95 GW and average neutron wall load of 3 MW/m
. This report covers various aspects of design study including systemic design, physics design, torus configuration, blanket, superconducting magnet, maintenance and building, which were carried out increase the engineering feasibility of the concept.
Ushigusa, Kenkichi; Seki, Masahiro; Ninomiya, Hiromasa; Norimatsu, Takayoshi*; Kamada, Yutaka; Mori, Masahiro; Okuno, Kiyoshi; Shibanuma, Kiyoshi; Inoue, Takashi; Sakamoto, Keishi; et al.
Genshiryoku Handobukku, p.906 - 1029, 2007/11
no abstracts in English
Tobita, Kenji; Nishio, Satoshi; Sato, Masayasu; Sakurai, Shinji; Hayashi, Takao; Shibama, Yusuke; Isono, Takaaki; Enoeda, Mikio; Nakamura, Hirofumi; Sato, Satoshi; et al.
Nuclear Fusion, 47(8), p.892 - 899, 2007/08
Times Cited Count：57 Percentile：86.6(Physics, Fluids & Plasmas)The concept for a compact DEMO reactor named "SlimCS" is presented. Distinctive features of the concept is low aspect ratio (
= 2.6) and use of a reduced-size center solenoid (CS) which has a function of plasma shaping rather than poloidal flux supply. The reduced-size CS enables us to introduce a thin toroidal field (TF) coil system which contributes to reducing the weight and construction cost of the reactor. SlimCS is as compact as advanced commercial reactor designs such as ARIES-RS and produces 1 GWe in spite of moderate requirements for plasma parameters. Merits of low-, i.e. vertical stability for high elongation and high beta limit are responsible for such reasonable physics requirements.
Tobita, Kenji; Nishio, Satoshi; Sato, Masayasu; Sakurai, Shinji; Hayashi, Takao; Shibama, Yusuke; Isono, Takaaki; Enoeda, Mikio; Nakamura, Hirofumi; Sato, Satoshi; et al.
Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2006/10
no abstracts in English
Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Sato, Masayasu; Isono, Takaaki; Sakurai, Shinji; Nakamura, Hirofumi; Sato, Satoshi; Suzuki, Satoshi; Ando, Masami; et al.
Fusion Engineering and Design, 81(8-14), p.1151 - 1158, 2006/02
Times Cited Count：123 Percentile：99.01(Nuclear Science & Technology)no abstracts in English
Wada, Ryutaro*; Nishimura, Tsutomu*; Nakanishi, Tomoaki*; Fujiwara, Kazuo*; Inoue, Takao*; Tateishi, Tsuyoshi*; Masugata, Tsuyoshi*
JNC TJ8400 2003-092, 246 Pages, 2003/02
JNC-TJ8400-2003-092.pdf:35.08MB
Titanium is being studied for the high-level radioactive waste package material. Titanium has good corrosion resistance, however there is the possibility of hydrogen embrittlement with absorption of hydrogen in reducing condition. Experimental studies were performed to evaluate the hydrogen absorption behaviors of titanium in reducing condition. The failure model of the titanium overpack was also examined from the viewpoint of fracture mechanism in order to evaluate the fracture behavior of the titanium overpack caused by the hydrogen absorption. (1) Scratch test was conducted in reduce condition. The surface films on the titanium specimen were analyzed to examine the changes of the existing films and the growth phenomena of the regenerated films on the titanium specimen. (2)The long-term reaction test of the titanium specimen using the glass-seal ampoules maintaining reducing condition was conducted and analyses of the hydrogen gas generation and absorption quantitative as well as the generated film evaluation were performed. (3) Under reducing condition, the electrochemical acceleration tests of the titanium specimen were conducted. The effect of acceleration rate on the hydrogen absorption and surface film was evaluated, and the prediction as to the hydrogen absorption behavior at a natural state was also made. (4) The prediction of the maximum residual stress and the evaluation of crack growth of the titanium overpack based on the previous studies were performed. Feasibility of the modeling of fracture phenomenon with existing analysis technique was examined and the items to be developed were also discussed.
Kuriyama, Masaaki; Akino, Noboru; *; Ito, Takao; Inoue, Takashi; Usui, Katsutomi; Ebisawa, Noboru; Oshima, Katsumi*; Ohara, Yoshihiro; Ohara, Hiroshi; et al.
Fusion Engineering and Design, 39-40, p.115 - 121, 1998/00
Times Cited Count：36 Percentile：91.63(Nuclear Science & Technology)no abstracts in English
Watanabe, Kazuhiro; ; Aoyagi, Tetsuo; ; Fujiwara, Yukio; Honda, Atsushi; Inoue, Takashi; Ito, Takao; Kawai, Mikito; Kazawa, Minoru; et al.
Radiation Physics and Chemistry, 49(6), p.631 - 639, 1997/00
Times Cited Count：3 Percentile：30.37(Chemistry, Physical)no abstracts in English
Kuriyama, Masaaki; Aoyagi, Tetsuo; ; *; Ito, Takao; Inoue, Takashi; Usami, H*; Usui, Katsutomi; ; Oshima, Katsumi*; et al.
Nihon Genshiryoku Gakkai-Shi, 38(11), p.912 - 922, 1996/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Kuriyama, Masaaki; Ohara, Yoshihiro; ; ; Hanada, Masaya; Inoue, Takashi; *; *; Ito, Takao; Kawai, Mikito; et al.
Fusion Technology 1992, Vol.1, p.564 - 568, 1993/00
no abstracts in English
Sawada, Yoshihisa*; Komatsu, Fumiaki*; Takagi, Yuji*; Mizoguchi, Takao*; Kobayashi, Masato*; Inoue, Takao*; Iwata, Toshio*; Wada, Ryutaro*
PNC TJ4058 88-004, 259 Pages, 1988/07
None
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
Chimi, Yasuhiro; Hanawa, Satoshi; Nishiyama, Yutaka; Nakamura, Takehiko; Tahara, Yuki*; Kojima, Takao*; Inoue, Hiroyuki*; Iwase, Akihiro*
no journal, ,
In order to understand irradiation effects on measurement of electrochemical corrosion potential (ECP), we have investigated the irradiation effects on component materials of zirconia membrane type ECP sensors. In the present report, we will present the change in properties of yttria(YO
)-stabilized zirconia(ZrO) (YSZ), which is used as the membrane, irradiated with energetic heavy ions. After irradiation with 200-MeV Xe ions up to 1
10
ions/cm at room temperature, the lattice parameter of YSZ specimens increases beyond about 0.5% of initial value. Micro-Vickers hardness of the specimens also increases with ion fluence. Considering the damage in YSZ by Xe-ion irradiation (about 0.2 dpa maximum), in case of in-core use of zirconia membrane type ECP sensors, neutron irradiation can affect the durability of a junction between YSZ and metal housing in the sensors.
Sumiya, Masato; Ikeda, Koki; Sonoda, Takashi; Niizato, Tadafumi; Mikake, Shinichiro; Abe, Hironobu; Inoue, Makoto; Eguchi, Kazutoshi; Kozawa, Masachiyo; Terunuma, Akihiro; et al.
no journal, ,
no abstracts in English
-ray irradiationInoue, Hiroyuki*; Hata, Kuniki; Idehara, Ryuichi*; Kojima, Takao*; Kasahara, Shigeki; Iwase, Akihiro*; Ueno, Fumiyoshi
no journal, ,
no abstracts in English
