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Suzuki, Masaaki*; Ito, Mari*; Hashidate, Ryuta; Takahashi, Keita; Yada, Hiroki; Takaya, Shigeru
2020 9th International Congress on Advanced Applied Informatics (IIAI-AAI 2020), p.797 - 801, 2021/07
Ishiyama, Shintaro; Minami, Mamoru*
Journal of Bioinformatics and Biological Engineering (Internet), 2(1), p.63 - 74, 2014/11
New control scheme Move on Sensing (MOS) technology was proposed and demonstrated its great potential as autonomous control system to be able to respond to interaction with growing simulation environment of differentiated iPS cells and the following results are derived; (1) Remove of the targeted cell models is completed by 20 times selection process from original cell group model composed of 20 red and 20 blue colored beads within 16 sec per cell. (2) High-accuracy sorting operation of iPS cell model was achieved within 16 sec per cell. (3) Retrievability of the discrete cell models isolated from group model is ensured by use of the MOS control.
Ishida, Hisashi
Proteins: Structure, Function, and Bioinformatics, 82(9), p.1985 - 1999, 2014/09
Times Cited Count：10 Percentile：33.71(Biochemistry & Molecular Biology)Li, H.*; Sakuraba, Shun; Chandrasekaran, A.*; Yang, L.-W.*
Journal of Chemical Information and Modeling, 54(8), p.2275 - 2285, 2014/08
Times Cited Count：15 Percentile：68.42(Chemistry, Medicinal)We provide evidence supporting that protein-protein and protein-ligand docking poses are functions of protein shape and intrinsic dynamics. Over sets of 68 protein-protein complexes and 240 non-homologous enzymes, we recognize common predispositions for binding sites to have minimal vibrations and angular momenta while two interacting proteins orient so as to maximize the angle between their rotation/bending axes (
). The findings are then used to define quantitative criteria to filter out docking decoys less likely to be the near-native poses, hence the chances to find near-native hits can be doubled. With the novel approach to partition a protein into `domains' of robust but disparate intrinsic dynamics, 90% of catalytic residues in enzymes can be found within the first 50% of the residues closest to the interface of these dynamics domains. The results suggest an anisotropic rather than isotropic distribution of catalytic residues near the mass centers of enzymes.
Koide, Kaoru; Koike, Katsuaki*
International Journal of Applied Earth Observation and Geoinformation, 19, p.88 - 103, 2012/10
Times Cited Count：6 Percentile：24.36(Remote Sensing)This paper presents a method for detecting high water-table areas based on vegetation information in a humid warm-temperate forest area using remotely sensed data (SPOT). The purpose is to develop methodologies for characterizing hydrogeological structures at a regional scale. To detect differences in vegetation conditions due to groundwater supply, a new vegetation index (AgbNDVI) and a segmentation analysis based on geographical characteristics were proposed. A study area was selected in the Tono region of central Japan. As a result, most of the high-VI points are located on the concave/convex slopes, in the vicinity of geologic boundaries, around groundwater seeps and in high water-table areas. Therefore, high-VI points can be a crucial marker for estimating hydraulic properties of geologic structures and groundwater flow regime. Consequently, the proposed method can be an useful tool to detect high water-table areas in humid warm-temperate forest areas.
Hoshiya, Taiji; Nishimura, Akihiko; Nishikawa, Masahiro*
Literacy Information and Computer Education Journal (Internet), 3(2), p.694 - 706, 2012/06
The Kids' Science Museum of Photons, which is attached to the Kansai Photon Science Institute of the JAEA and is managed as an unique and experienced study type of museum with the theme of the photon science, provides us with the mystery of light through various exhibits, theater, and experimental events. In this research, the outline of science communication activities of energy and environmental education such as recent coordinated course, the experiment booth village and the science-walker is discussed in the degree of understanding, inquiring mind and its effects.
Morita, Yasuji; Kimura, Takaumi
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), p.235 - 244, 2012/00
Separation process for transuranium elements (TRU = Am, Cm, Np and Pu) and some fission products (Sr, Cs and Mo) has been developed at Japan Atomic Energy Agency using new innovative extractants and adsorbents to improve the partitioning process from viewpoints of the economy and the reduction of secondary wastes. Phosphorus-free compounds consisting of carbon, hydrogen, oxygen and nitrogen (CHON principle) were applied to the separation steps for TRU, Cs and Sr by using solvent extraction or extraction chromatography. Mo is separated by adsorption with an iron oxide adsorbent. This paper gives results of the research and development of the separation process.
Sato, Takumi; Nishihara, Kenji; Hayashi, Hirokazu; Kurata, Masaki*; Arai, Yasuo
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), 9 Pages, 2012/00
Nitride fuel cycle for transmutation of long-lived minor actinides (MAs) has been developed in Japan Atomic Energy Agency (JAEA) under the double-strata nuclear fuel cycle concept. This study aims at developing the process flow diagram with the material balance sheet of the pyrochemical reprocessing of spent nitride fuel for ADS to evaluate the technological feasibility of the fuel cycle. Three process flow diagrams were proposed in this work: (1) the currently-proposed process with the molten salt electrorefining of spent nitride fuel, (2) the process with the molten salt electrorefining of the actinide-cadmium alloy after the chemical dissolution of spent nitride fuel, and, (3) the process combining the chemical dissolution of spent nitride fuel and the multi-stage counter current extraction. Moreover, the material balance was evaluated for the process (1) by use of the calculated and experimental data of the nitride fuel for ADS.
Matsumura, Tatsuro; Morita, Yasuji; Matsumura, Kazumi; Sano, Yuichi; Koma, Yoshikazu; Nomura, Kazunori
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), 8 Pages, 2012/00
no abstracts in English
Minato, Kazuo; Morita, Yasuji; Tsujimoto, Kazufumi; Koyama, Shinichi; Kurata, Masaki*; Inoue, Tadashi*; Ikeda, Kazumi*
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), p.341 - 349, 2012/00
In order to provide a quantitative assessment for the maturity of the partitioning and transmutation technology relative to its full-scale deployment, a technology readiness level (TRL) process was used. The definitions of TRL used in this study were based on those used in the Global Nuclear Energy Partnership (GNEP). The TRL was evaluated and the technology pathway was discussed for the systems of FBR and ADS for the minor actinides (MA) transmutation, MA partitioning processes, and MA-bearing fuels. Through the evaluation, it was recognized that hard requirements to be satisfied were present at TRL 5 for each technology development. The introduction of lab-scale tests with actual spent fuel for MA partitioning process and with actual separated materials for MA-bearing fuels fabrication and irradiation before the engineering scale tests may be effective and efficient solution.
Nishihara, Kenji; Sugawara, Takanori; Iwamoto, Hiroki; Alvarez Velarde, F.*; Rineiski, A.*
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), p.315 - 327, 2012/00
Accuracy of nuclear data, especially for minor actinides (MAs), is important in neutronics design of advanced reactors for MA transmutation such as an Accelerator-Driven System (ADS). Authors introduce the results of a benchmark activity in the IAEA CRP that revealed a discrepancy among k-effectives by different nuclear data libraries is as large as 3% even for an initial criticality before burn-up. In order to reduce this uncertainty, Transmutation Physics Experimental Facility (TEF-P) with a significant amount of MA is being proposed in the J-PARC project. An expected reduction of the uncertainty of criticality, void reactivity and Doppler coefficient by the TEF-P was numerically evaluated using the cross-section adjustment procedure based on the JENDL3.3. The uncertainty would be reduced from 1.3% to 0.6% if experimental results of the TEF-P and other past critical experiments were utilized to adjust nuclear data.
Tomiyama, Shin*; Mimura, Hitoshi*; Niibori, Yuichi*; Yamagishi, Isao; Morita, Yasuji
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), 10 Pages, 2012/00
The immobilization of Cs has been studied by the calcination of the Cs-form of various kinds of mordenites. In this study, the effect of various parameters such as calcining temperature and time, components in mordenites, conditions for cold and hot pressing, on the immobilization of Cs in ceramic products are evaluated by using X-ray diffractometry (XRD), density balance (Archimedes' method), scanning electron microscopy (SEM) and electron probe microanalysis (EPMA). Results showed that recrystallization to the stable ceramic solid forms of CsAlSi
O
was achieved only in calcination of Synthetic Mordenite-C which contains Ti and Fe as binder. The Cs-form mordenites were pelletized into a disk by cold isostatic pressing and the density of the solid forms increased with calcining temperature and time.
Oigawa, Hiroyuki; Minato, Kazuo; Morita, Yasuji; Kimura, Takaumi; Arai, Yasuo; Tsujimoto, Kazufumi; Nishihara, Kenji
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), p.123 - 132, 2010/11
After the first check and review on the partitioning and transmutation (PT) technology by the Japan Atomic Energy Commission (JAEC) in 2000, significant progress was made in respective research areas of the partitioning, fuel fabrication, transmutation and fuel recycling in Japan. The second check and review on the PT technology was made by the JAEC in 2008-2009. The final report issued in April, 2009, mentions that the significance of the PT technology is in three points: reduction of the potential hazard, mitigation of the requirement for geological repository site, and enhancement of the options in the design of the whole system of waste disposal. The current technology levels of the PT for both FBR and ADS were evaluated. The PT technology in general is still in the basic research because of the lack of experimental data for minor actinides (MA). It was, therefore, strongly recommended to accumulate the experimental data for MA as a common basis for both FBR and ADS.
Hayashi, Hirokazu; Akabori, Mitsuo; Arai, Yasuo; Minato, Kazuo
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 9 Pages, 2010/00
R&D on the transmutation of long-lived minor actinides (MA) by the accelerator-driven system (ADS) using nitride fuels is underway at JAEA. In regard to reprocessing technology, pyrochemical process has several advantages in case of treating spent fuel with large decay heat and fast neutron emission, and recovering highly enriched 
N. In the pyrochemical reprocessing, plutonium and MA are dissolved in LiCl-KCl eutectic melts and selectively recovered into liquid cadmium cathode by molten salt electrorefining. The electrochemical behavior in LiCl-KCl eutectic melts and the subsequent nitride formation behavior of plutonium and MA recovered in liquid Cd cathode are investigated. Recent results on the behavior of americium (Am) in the pyrochemical process for the treatment of spent nitride fuel, which include preparation of AmCl
and electrochemical behavior of Am in LiCl-KCl eutectic melts, are presented.
Kato, Masato; Morimoto, Kyoichi; Komeno, Akira; Nakamichi, Shinya; Kashimura, Motoaki
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), p.201 - 209, 2010/00
Japan Atomic Energy Agency has developed homogeneous MOX fuel containing minor actinide (MA) elements such as Np and Am. To measure physical properties of the fuel is essential for its development, because their data are needed to evaluate irradiation behavior. In this report, the physical properties, melting temperature, thermal conductivity, lattice parameter, oxygen potential and phase separation behavior, were reviewed, and effect of MA content was discussed.
Sugawara, Takanori; Suzuki, Kazuhiko; Nishihara, Kenji; Sasa, Toshinobu; Kurata, Yuji; Kikuchi, Kenji; Oigawa, Hiroyuki
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 11 Pages, 2010/00
The investigations of the beam window which is one of the most critical components for the Accelerator Driven System (ADS) were performed. In the previous study, it was found that the buckling failure was the most severe failure mode for the beam window. Hence, the shape and the thickness of the beam window were optimized to prevent the buckling failure. The buckling analyses with initial imperfections were also performed to identify the level of the factor of safety (FS). The results showed that FS of 3 was conservative enough to ensure the integrity of the beam window. It was also shown that the ellipse shape concepts with the thickness of 2.0-2.4[mm] at the top and the thickness of 2.0-4.0[mm] at the transient part were acceptable under the current ADS design parameters.
Sugawara, Takanori; Sasa, Toshinobu; Oigawa, Hiroyuki
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 10 Pages, 2010/00
Improvement on the neutronics design accuracy of the MA-loaded core is one of the most important issues in the MA transmutation technologies. Uncertainties of the current MA nuclear data are supposed to be larger than those of other major nuclides. Therefore, analyzed neutronics properties of MA-loaded FR and ADS have much larger design margins in comparison with those of conventional FR. To improve the reliability, safety and economical efficiency of these systems, it is required to increase the accuracy of the nuclear data of MA by the experimental data taken under adequate experimental conditions. In this study, error analyses were conducted to estimate the benefit of the MA-loaded experiments at TEF-P (Transmutation Physics Experimental Facility) on the error reduction in neutronics design of transmutation systems. Through this estimation, the effect of the MA-loaded experiments at TEF-P was verified quantitatively.
Kurata, Yuji; Saito, Shigeru
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 11 Pages, 2010/00
Corrosion tests of various steels in liquid Pb-Bi have been conducted using static corrosion apparatus to study corrosion behaviour in liquid Pb-Bi, a promising candidate material of coolants and high-power spallation targets of accelerator driven systems for transmutation of radioactive wastes. Effects of temperature, oxygen concentration in Pb-Bi and elements in steels on corrosion behavior were estimated from test results. Tested temperature range was from 450
C to 600C. Temperature increase produced active corrosion and grain boundary corrosion, penetration of Pb-Bi and ferritization became severe above 550C. Effect of oxygen concentration was clearly found in pure iron and 316SS at 450C and corrosion attack became severe under the low oxygen concentration condition at 550C. Mod.9Cr-1Mo with addition of 1.5%Si and 316SS with addition of 2.5%Si showed good corrosion resistance in liquid oxygen-saturated Pb-Bi at 550C.
-tetradodecyl-diglycolamideSasaki, Yuji; Asakura, Toshihide; Kitatsuji, Yoshihiro; Morita, Yasuji; Kimura, Takaumi
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 6 Pages, 2010/00
Diglycolamide, DGA, compounds have the strong extractability with trivalent, tetravalent and hexavalent actinides (An) from nitric acid to n-dodecane. Since DGA connecting with the long alkyl chain, TDdDGA (-tetradodecyl-diglycolamide), has the high extraction capacity and suppresses to form the third phase with Nd, we used TDdDGA to demonstrate the counter-current extraction, prior to the hot test. In this experiment we use four elements, i.e., Sr, Pd, Zr and Nd, as the typical fission products and a representative ion of An(III) and lanthanides, to confirm the extraction and the separation properties, these four elements are extractable by TDdDGA. After determination of the optimum condition on the extraction and separation of Nd from other elements by the calculation using D values, we perform the counter-current extraction using the mixer-settler equipment.
Takano, Masahide; Akabori, Mitsuo; Arai, Yasuo; Minato, Kazuo
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 7 Pages, 2010/00
As the research activities concerning the nitride fuel for the transmutation of minor actinides, the lattice thermal expansions of the transuranium nitrides were investigated in order to build the material database. The lattice parameters of NpN, PuN and AmN were measured by the high temperature X-ray diffraction method from room temperature to 1478 K. Their linear thermal expansions were determined as a function of temperature. The average thermal expansion coefficients over the temperature range of 293 to 1273 K for these nitrides were 8.8, 11.1 and 11.2
10
K
, respectively. Further, the thermal expansions of the nitride solid solution samples, (Np,Am)N, (Pu,Am)N, (Np,Pu,Am,Cm)N and (Pu,Am,Zr)N, were measured to investigate the composition dependence. It was confirmed that the average thermal expansion coefficients for these solid solution samples could be approximated by the linear mixture rule within the error of 2
3%.
