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Yoshida, Koji*; Inoue, Takuya*; Torigoe, Motokatsu*; Yamada, Takeshi*; Shibata, Kaoru; Yamaguchi, Toshio*
Journal of Chemical Physics, 149(12), p.124502_1 - 124502_10, 2018/09
Times Cited Count：4 Percentile：17.83(Chemistry, Physical)Differential scanning calorimetry, X-ray diffraction, and quasi-elastic neutron scattering (QENS) measurements of aqueous glycine solutions confined in mesoporous silica (MCM-41) were performed at different glycine concentrations, pH, and loading ratio (= mass of glycine solution / mass of dry MCM-41) in the temperature range from 305 to 180 K to discuss the confinement effect on the thermal behavior, the structure, and the dynamic properties of the solutions.
Ozeki, Hidemasa; Isono, Takaaki; Kawano, Katsumi; Saito, Toru; Kawasaki, Tsutomu; Nishino, Katsumi; Okuno, Kiyoshi; Kido, Shuichi*; Semba, Tomoyuki*; Suzuki, Yozo*; et al.
IEEE Transactions on Applied Superconductivity, 25(3), p.4200804_1 - 4200804_4, 2015/06
Times Cited Count：0 Percentile：0(Engineering, Electrical & Electronic)Yogo, Akifumi; Kondo, Kiminori; Mori, Michiaki; Kiriyama, Hiromitsu; Ogura, Koichi; Shimomura, Takuya; Inoue, Norihiro*; Fukuda, Yuji; Sakaki, Hironao; Jinno, Satoshi; et al.
Optics Express (Internet), 22(2), p.2060 - 2069, 2014/01
Times Cited Count：10 Percentile：49.33(Optics)Izumo, Hironobu; Chimi, Yasuhiro; Ishida, Takuya; Kawamata, Kazuo; Inoue, Shuichi; Ide, Hiroshi; Saito, Takashi; Ise, Hideo; Miwa, Yukio; Ugachi, Hirokazu; et al.
JAEA-Technology 2009-011, 31 Pages, 2009/04
JAEA-Technology-2009-011.pdf:4.38MB
Regarding Irradiation Assisted Stress Corrosion Cracking (IASCC) for austenitic stainless steel of the light water reactor (LWR), a lot of data that concerns the post irradiation evaluation (PIE) is acquired. However, IASCC occurs in LWR condition. Therefore, it is necessary to confirm adequacy of the PIE data comparing the experiment data under the simulated LWR condition. Bigger specimen is needed to acquire the effective data for the destruction dynamics in the study of stress corrosion cracking under neutron irradiation condition. Therefore, development of a new crack growth unit which can load to bigger is necessary to the neutron irradiation test. As a result, a prospect was provided in the unit that could load to specimen by changing load mechanism to the lever type from the linear type. And also, in the development of crack propagation unit, some technical issues were extracted from the discussion of the unit structure adopting the LVDT (Linear Variable Differential Transformer).
Tomita, Kenji; Inoue, Shuichi; Ishida, Takuya; Onuma, Yuichi; Tsuchiya, Kunihiko
JAEA-Technology 2008-050, 41 Pages, 2008/07
JAEA-Technology-2008-050.pdf:6.6MB
Blanket Functional Facility (BFT) for fusion blanket development was established in the Japan Materials Testing Reactor (JMTR). The irradiation tests with Li
TiO
pebble-bed were carried out with the BFT. The BFT was constituted a sweep gas device for tritium measurement and recover and a capsule controlled device for temperature control and neutron flux measurement of LiTiO pebble-bed. Five tritium monitors (ion chambers) for tritium measurement were established in the sweep gas device. In these tritium monitors, one tritium monitor for the measurement of tritium release property (TmIRA201) was not able to be used and it is necessary to exchange new tritium monitors. This report is described the fabrication of new tritium monitors and exchange procedure of this monitors.
Ide, Hiroshi; Matsui, Yoshinori; Kawamata, Kazuo; Taguchi, Taketoshi; Kanazawa, Yoshiharu; Onuma, Yuichi; Watanabe, Hiroyuki; Inoue, Shuichi; Izumo, Hironobu; Ishida, Takuya; et al.
JAEA-Technology 2008-012, 36 Pages, 2008/03
JAEA-Technology-2008-012.pdf:10.09MB
It is known that Irradiation Assisted Stress Corrosion Cracking (IASCC) occurs when austenitic stainless steel components used for light water reactor (LWR) are irradiated for a long period. In order to evaluate the high aging of the nuclear power plant, the study of IASCC becomes the important problem. The specimens irradiated in the reactor were evaluated by post irradiation examination in the past study. For the appropriate evaluation of IASCC, It is necessary to test it under the simulated LWR conditions; temperature, water chemistry and irradiation conditions. In order to perform in-pile SCC test, saturated temperature capsule (SATCAP) was developed. There are crack growth test, crack propagation test and so on for in-pile SCC test. In this report, SATCAP for crack propagation test is reported.
Ide, Hiroshi; Matsui, Yoshinori; Kawamata, Kazuo; Taguchi, Taketoshi; Kanazawa, Yoshiharu; Onuma, Yuichi; Watanabe, Hiroyuki; Inoue, Shuichi; Izumo, Hironobu; Ishida, Takuya; et al.
JAEA-Technology 2008-011, 46 Pages, 2008/03
JAEA-Technology-2008-011.pdf:19.39MB
It is known that Irradiation Assisted Stress Corrosion Cracking (IASCC) occurs when austenitic stainless steel components used for light water reactor (LWR) are irradiated for a long period. In order to evaluate the high aging of the nuclear power plant, the study of IASCC becomes the important problem. The specimens irradiated in the reactor were evaluated by post irradiation examination in the past study. For the appropriate evaluation of IASCC, It is necessary to test it under the simulated LWR conditions; temperature, water chemistry and irradiation conditions. In order to perform in-pile SCC test, saturated temperature capsule (SATCAP) was developed. There are crack growth test, crack propagation test and so on for in-pile SCC test. In this report, SATCAP for crack growth test is reported.
Hayashi, Takumi; Konishi, Satoshi; Yamada, Masayuki; Matsuda, Yuji; Inoue, Masahiko; Nakamura, Takuya; Takanaga, M.; Naruse, Yuji; Okuyama, Nobuhisa*
Fusion Technology, 19(3P2B), p.1663 - 1667, 1991/05
no abstracts in English
Inoue, Naoko; Irie, Tsutomu; Kitabata, Takuya; Rochau, G.*; York, D.*; Mendez, C.*
no journal, ,
Japan Atomic Energy Agency (JAEA) and Sandia National Laboratories (SNL) have entered cooperative program, in 2005, to demonstrate a methodology capable assessing proliferation risk in support of overall plant transparency. Earlier, both organizations have preliminary discussion to develop the methodology. The Advanced Fuel Cycle Transparency Framework Concept is being implemented at the Fuel Handling Training Model designed for "Monju", prototype Fast Reactor at the International Nuclear Information and Training Center (ITC) of Tsuruga Head Office, the Japan Atomic Energy Agency (JAEA). "Monju" is fully automated facility and the training model reproducts the entire Monju fuel handling process. The training model is used to generate and transmit information to a secure database at ITC located by Monju site. A computer syncronized to the visible movements in the model mimicking process data supply data. The database is accessible to analyst at SNL via encryption and virtual private network (VPN). The data stream is fed into the "Transparency Software" for real time analysis when the model is being exeicised. "Transparency Software" is expected to monitor the information from the model and to calcurate the prolifearation risk by compared with expected values. This concept will be able to expamd the ability to enable effective transparency system in the aspect of safety and lagitmate use of nuclear material and technology, to contribute the transparency concept among international communities or between a state and IAEA, for the future nuclear fuel cycles. This paper will describe the concept, implememtation plan and status of the demonstration project, and progress toward the first demonstration of the system.
Kitabata, Takuya; Inoue, Naoko; Irie, Tsutomu; Rochau, G.*; Cleary, V.*; York, D.*
no journal, ,
An experimental system of "Transparency Framework" was completed connecting the output signal of the fuel handling training model of the Prototype Fast Breeder Reactor, "Monju" and server computers in the Sandia National Laboratory. The system determines a proliferation risk of the model on a real-time basis using a risk evaluation method. A prospect for application of the "Transparency Framework" to future nuclear systems is discussed.
Katsumura, Soichiro; Suzuki, Mitsutoshi; Hashimoto, Yu; Inoue, Naoko; Kitabata, Takuya; Irie, Tsutomu; Rochau, G.*; Cleary, V.*; Mcfadden, K.*; Mendez, C.*
no journal, ,
no abstracts in English
Yogo, Akifumi; Inoue, Norihiro*; Sakaki, Hironao; Fukuda, Yuji; Jinno, Satoshi; Kanasaki, Masato; Kiriyama, Hiromitsu; Shimomura, Takuya; Ogura, Koichi; Mori, Michiaki; et al.
no journal, ,
The laser-ion acceleration can be complicated by the presence of an amplified spontaneous emission (ASE) pedestal at a leading edge of the high-intensity laser pulse. Several attempts have been made to decrease the ASE level by using a plasma mirror or a OPCPA laser system combined with a saturable absorber: J-KAREN. In this work, we propose another way to improve the main pulse-ASE ratio by using a double-CPA bypass line system. We have developed a new laser line consisting of a pulse compressor, a saturable absorber, a pulse stretcher and a Ti:Sap. multi-pass amplifier. The most remarkable feature of this system is that the bypass line can be installed into a conventional TW laser system.
Handa, Takuya; Enuma, Yasuhiro; Ono, Yukihiko*; Nakamura, Yuki*; Sakata, Nobuyasu*; Kushioka, Kiyonori*; Shimoji, Kuniyuki*; Inoue, Tomoyuki*; Matsumoto, Iwao*
no journal, ,
no abstracts in English
Enuma, Yasuhiro; Handa, Takuya; Shimazaki, Masanori*; Ono, Yukihiko*; Yoshida, Kazuhiro*; Hayakawa, Satoshi*; Inoue, Tomoyuki*
no journal, ,
no abstracts in English
Ozeki, Hidemasa; Isono, Takaaki; Kawano, Katsumi; Saito, Toru; Kawasaki, Tsutomu; Nishino, Katsumi; Okuno, Kiyoshi; Kido, Shuichi*; Semba, Tomoyuki*; Suzuki, Yozo*; et al.
no journal, ,
no abstracts in English
Yoshii, Kenji; Tsuji, Takuya; Matsumura, Daiju; Nishida, Ginichi*; Inoue, Naoki*; Fukada, Yukimasa*; Yaita, Tsuyoshi
no journal, ,
We have investigated the magnetic properties of Bi-doped perovskite GdCrO, which was reported to be multiferroic below the magnetic transition temperature (170 K). For the low doping levels (about 5-10% Bi at the Gd site), single-phase samples could be prepared at 920
C, a temperature which is much lower than the firing temperature of GdCrO (about 1300-1400C). This result is essentially the same as that of isostructural (Sm,Bi)CrO. Magnetic measurements showed that the magnetic properties were essentially identical to those of GdCrO. For example, the chromium spins show a ferrimagnetic transition at 170 K. Interestingly, these properties were entirely different from those of (Sm,Bi)CrO, which showed that the Bi doping led to a drastic lowering of magnetic transition temperature (by 140 K). We have also conducted X-ray absorption measurements to determine the crystallographic site of Bi. The results will be shown at the conference.
