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Kobayashi, Takane*; Onishi, Tsuyoshi*; Osawa, Takahito; Pratt, A.*; Tear, S.*; Shimoda, Susumu*; Baba, Hidetada*; Laitinen, M.*; Sajavaara, T.*
Small, 18(46), p.2204455_1 - 2204455_9, 2022/11
Times Cited Count：5 Percentile：32.25(Chemistry, Multidisciplinary)An all-solid-state battery is a secondary battery that is charged and discharged by the transport of lithium ions between positive and negative electrodes. To fully realize the significant benefits of this battery technology, for example, higher energy densities, faster charging times, safer operation, it will be essential to understand how lithium ions are transported and distributed in the battery during operation. However, as the third lightest element, methods for quantitatively analyzing lithium during operation of an all-solid-state device are limited such that real time tracking of lithium transport has not yet been demonstrated. Here, we report that the transport of lithium ions in an all-solid-state half-cell was quantitatively tracked in near real time by utilizing a thermal neutron-induced nuclear reaction, utilizing lithium-6 as a tracer, and utilizing a high-intensity thermal neutron source. Furthermore, it is also mentioned that the migration mechanism and migration region of lithium ions in the solid electrolyte used could be determined by tracking the transport of lithium ions. From these results, it can be said that the development of all-solid-state batteries has entered a phase where further advances could be carried out while understanding the transport of lithium ions in the batteries. As a result, the research and development of all-solid-state batteries would be further accelerated.
Kim, S. B.*; Lee, K.-H.*; Raj, M. S.*; Reeder, J. T.*; Koo, J.*; Hourlier-Fargette, A.*; Bandodkar, A. J.*; Won, S. M.*; Sekine, Yurina; Choi, J.*; et al.
Small, 14(45), p.1802876_1 - 1802876_9, 2018/11
Times Cited Count：79 Percentile：93.88(Chemistry, Multidisciplinary)Excretion of sweat from eccrine glands is a dynamic physiological process that varies with body position, activity level, and health status. Information content embodied in sweat rate and chemistry can be used to assess health status and athletic performance. This paper presents a thin, miniaturized, skin-interfaced microfluidic technology that includes a reusable, battery-free electronics module for measuring sweat conductivity and rate in real-time using wireless power from and data communication with capabilities in near field communications (NFC). Systematic studies of these combined microfluidic/electronic systems, accurate correlations of measurements performed with them to those of laboratory standard instrumentation, and field tests on human subjects establish the key operational features and their utility in sweat analytics.
Saptiama, I.*; Kaneti, Y. V.*; Suzuki, Yoshitaka; Tsuchiya, Kunihiko; Fukumitsu, Nobuyoshi*; Sakae, Takeji*; Kim, J.*; Kang, Y.-M.*; Ariga, Katsuhiko*; Yamauchi, Yusuke*
Small, 14(21), p.1800474_1 - 1800474_14, 2018/05
Times Cited Count：52 Percentile：89.44(Chemistry, Multidisciplinary)no abstracts in English
Kim, S. B.*; Zhang, Y.*; Won, S. M.*; Bandodkar, A. J.*; Sekine, Yurina; Xue, Y.*; Koo, J.*; Harshman, S. W.*; Martin, J. A.*; Park, J. M.*; et al.
Small, 14(12), p.1703334_1 - 1703334_11, 2018/03
Times Cited Count：100 Percentile：95.69(Chemistry, Multidisciplinary)
superstructure of monolayer MoS
and MoSe on Au(111)Yasuda, Satoshi; Takahashi, Ryosuke*; Osaka, Ryo*; Kumagai, Ryota*; Miyata, Yasumitsu*; Okada, Susumu*; Hayamizu, Yuhei*; Murakoshi, Kei*
Small, 13(31), p.1700748_1 - 1700748_8, 2017/08
Times Cited Count：25 Percentile：72.37(Chemistry, Multidisciplinary)MoS and MoSe monolayers are grown on Au surface by chemical vapor deposition and it is demonstrated that the contact with a crystalline Au(111) surface gives rise to only out-of-plane strain in both MoS and MoSe layers, whereas no strain generation is observed on polycrystalline Au or SiO/Si surfaces. Scanning tunneling microscopy analysis provides information regarding consequent specific adsorption sites between lower S (Se) atoms in the S-Mo-S (Se-Mo-Se) structure and Au atoms via unique moir superstructure formation for MoS and MoSe layers on Au(111). This observation indicates that the specific adsorption sites give rise to out-of-plane strain in the TMDC layers. Furthermore, it also leads to effective modulation of the electronic structure of the MoS or MoSe layer.
Yamamoto, Masato*; Onizawa, Kunio; Yoshimoto, Kentaro*; Ogawa, Takuya*; Mabuchi, Yasuhiro*; Valo, M.*; Lambrecht, M.*; Viehrig, H.-W.*; Miura, Naoki*; Soneda, Naoki*
Small Specimen Test Techniques; 6th Volume (ASTM STP 1576), p.53 - 69, 2015/05
In order to ensure the robustness of the Master Curve technique, round-robin tests were performed using 0.16 inch-thick Mini-CT specimens by different investigators to see if consistent 
values can be obtained. All the specimens used were machined and pre-cracked by one fabricator from unique Japanese RPV material. Seven institutes participated in this exercise, and obtained valid values according to the ASTM E1921 standard. The scatter of values obtained was well within the uncertainty range defined in the standard, indicating the robustness of the Mini-CT specimen test technique. Throughout this activity, we could obtain 182 
for a single material. We investigated the statistics of this large database, and found that there is no remarkable difference not only in the values but also in the fracture toughness distribution between the Mini-CT specimen and the standard size 1T-C(T) specimen results.
Ito, Yuzuru; Saito, Masahiro*; Abe, Katsunori*; Wakai, Eiichi
Small Specimen Test Techniques; 6th Volume (ASTM STP 1576), p.209 - 224, 2015/00
Ohashi, Hirofumi; Sato, Hiroyuki; Tazawa, Yujiro; Yan, X.; Tachibana, Yukio; Kunitomi, Kazuhiko
Proceedings of ASME 2011 Small Modular Reactors Symposium (SMR 2011) (CD-ROM), 10 Pages, 2011/09
JAEA has started a conceptual design of a small-sized HTGR for steam supply and power generation (HTR50S), of which reactor power is 50 MWt and the reactor outlet temperature is 750
C, to deploy the HTGR in developing countries at an early date (i.e., in the 2030s). The major specifications of the HTR50S were determined based on its design philosophy, which is to upgrade its performance and to reduce the cost by utilizing the knowledge obtained by the HTTR operation and the GTHTR300 design. The system design of HTR50s was performed to offer the capability of electricity generation, cogeneration of electricity and steam for a district heating and industries. The market potential for the small-sized HTGR in the developing countries was evaluated for the application of the electricity, process heat, district heating and pure water production. It was confirmed that there is enough market potential for the small-sized HTGR in the developing countries.
Kurata, Yuji; Yokota, Hitoshi*; Suzuki, Tetsuya*
Proceedings of ASME 2011 Small Modular Reactors Symposium (SMR 2011) (CD-ROM), 7 Pages, 2011/09
Small and medium reactors using lead alloys as coolant are one of the promising reactor concepts with improved safety. This paper focuses on development of Al-alloy coating for nuclear systems using liquid lead-bismuth eutectic (LBE). Since corrosion attack becomes severe against steels at high temperatures, it is necessary to improve corrosion resistance. An Al-alloy coating method using Al, Ti and Fe powders, and laser beam heating has been developed. Main defects formed in an Al-powder-alloy coating process are surface defects and cracks. Conditions required to avoid these defects were found. According to results of the corrosion tests at 550 C in liquid LBE, the Al-alloy coating layers on 316SS protect severe corrosion attack observed in 316SS without coating. From the viewpoints of the soundness of coating layers and preservation of their corrosion resistance, it is estimated that the range of the adequate Al concentration in the coating layer is from 4 to 12 wt%.
Goto, Minoru; Shimakawa, Satoshi; Terada, Atsuhiko; Shibata, Taiju; Tachibana, Yukio; Kunitomi, Kazuhiko
Proceedings of ASME 2011 Small Modular Reactors Symposium (SMR 2011) (CD-ROM), 5 Pages, 2011/09
The present study challenges the core design of a small-sized reactor for long refueling interval by increasing core size, fuel loading and fuel burn up compared with the High Temperature engineering Test Reactor (HTTR). The core burn-up calculation suggested that approximately 6 years of long refueling interval was found to be reasonably achieved with operational reactor power of 120 MWt.
Iwamura, Takamichi; Ishikawa, Nobuyuki; Okubo, Tsutomu
Proceedings of 4th Asian Specialist Meeting on Future Small-Sized LWR Development, p.11_1 - 11_9, 2007/11
An advanced LWR concept of Innovative Water Reactor for Flexible fuel cycle (FLWR) has been established based on the well-experienced LWR technologies. The feature of this concept is that the high conversion type core (HC-FLWR) with small technical gap from current LWR technologies can be proceed to the breeding type FLWR core, named Reduced-Moderation Water Reactor (RMWR) under the same core configuration and reactor systems. This paper describes the investigations on designs and introduction scenario of FLWR.
Okubo, Tsutomu; Uchikawa, Sadao; Kugo, Teruhiko; Akie, Hiroshi; Iwamura, Takamichi
Proceedings of 3rd Asian Specialist Meeting on Future Small-sized LWR Development, p.9_1 - 9_12, 2005/11
A concept of Innovative Water Reactor for Flexible Fuel Cycle(FLWR) has been investigated in JAEA in order to ensure sustainable energy supply in the future based on the well-developed LWR technologies. The concept aims at effective and flexible utilization of uranium and plutonium resources through plutonium multiple recycling by two steps. In the first step, FLWR core realizes a high conversion type core concept, which is basically intended to keep the smooth technical continuity from current LWR and coming LWR-MOX technologies without significant gaps in technical point of view. The core in the second step represents the RMWR core concept, which realizes a high conversion ratio over 1.0 being useful for the long-term sustainable energy supply through plutonium multiple recycling based on the LWR technologies. The key point is that the core concepts in both steps utilize the compatible and the same size fuel assemblies, and hence during the reactor operation period, the former concept can proceed to the latter in the same reactor system, corresponding flexibly to the expected change in the future circumstances of natural uranium resource, or establishment of economical reprocessing technology for the MOX spent fuel. Detailed investigation have been performed on the core design, in conjunction with the other related studies such as on the thermal hydraulics in the tight-lattice core including the experimental activities, and the results obtained so far have shown that the proposed concept is feasible and promising. For commercial realization of the FLWRs in 2030s, a 400MWe class small reactor is proposed to be constructed in 2010s as a leading demonstration plant.
Iwamura, Takamichi; Okubo, Tsutomu
Proceedings of 2nd Asian Specialist Meeting on Future Small-Sized LWR Development, p.7_1 - 7_5, 2003/00
An innovative water-cooled reactor concept named Reduced-Moderation Water Reactor (RMWR) is under development at JAERI, aiming at effective fuel utilization through plutonium (Pu) multiple recycling based on the well-experienced water-cooled reactor technology. The reactor is able to achieve a high conversion ratio more than 1.0 with MOX fuel, to establish the sustainable Pu recycling. Such a high conversion ratio can be attained by reducing the moderation of neutrons, i.e. reducing the water fraction in the core. Detailed research and development activities have been performed on the core design, in conjunction with the other related studies such as on the thermal hydraulics in the tight-lattice core, the reactor physics and the fuel irradiation behavior, including the experimental activities. Also, for the total feasibility demonstration of the RMWR technologies, a design investigation for Reduced-Moderation Demonstration Reactor (RMDR) of 180MWt is being performed.
Iwamura, Takamichi; Ochiai, Masaaki
Proceedings of 1st Asian Specialist Meeting of Future Small-Sized LWR Development, p.7_1 - 7_9, 2001/00
JAERI has developed two types of small and medium size Light Water Reactors to meet the goals of innovative nuclear reactors such as sustainability and diversification of energy utilization. One is the Reduced-Moderation light Water Reactor (RMWR) with passive safety features. The reactor core consists of MOX fuel assemblies with tight lattice arrangement to increase the conversion ratio by reducing the moderation of neutron energy. The core design of 330MWe output with the operational cycle of 26 months was accomplished. A breeding ratio of 1.01, negative void coefficient and natural circulation cooling of the core were realized under the discharged burn-up of 60GWd/t. The other is the Passive Safe small Reactor for Distributed energy systems (PSRD) to diversify the nuclear energy utilization. An innovative advanced marine reactor (MRX) is used to supply the small grid electricity or electricity and heat co-supply by installing it on a barge. A small integral LWR for underground deployment is also studied for exclusive use of heat supply to household or office.
Sugimoto, Masayoshi
Proc. of Int. Workshop on Controls for Small-and Medium-Scale Accelerators, 0, p.115 - 117, 1998/00
no abstracts in English
Onizawa, Kunio; E.van-Walle*; R.K.Nanstad*; M.Sokolov*; W.Pavinich*
Small Specimen Test Techniques (ASTM STP 1329), 0, p.383 - 410, 1998/00
no abstracts in English
Nishiyama, Yutaka; Fukaya, Kiyoshi; Onizawa, Kunio; Suzuki, Masahide; *; *; *; *
Small Specimen Test Techniques (ASTM STP 1329), 0, p.484 - 494, 1998/00
no abstracts in English
Jitsukawa, Shiro; Kizaki, Minoru; ; Shiba, Kiyoyuki; Hishinuma, Akimichi
Small Specimen Test Techniques; ASTM STP 1204, p.289 - 307, 1993/00
Times Cited Count：15 Percentile：98.51(Nuclear Science & Technology)no abstracts in English
Suzuki, Masahide; Eto, Motokuni; Nishiyama, Yutaka; Fukaya, Kiyoshi;
Small Specimen Test Techniques; ASTM STP 1204, p.217 - 227, 1993/00
no abstracts in English
Nishiyama, Yutaka; Fukaya, Kiyoshi; Suzuki, Masahide; Eto, Motokuni; *
Small Specimen Test Techniques; ASTM STP 1204, p.16 - 26, 1993/00
no abstracts in English
