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Hidaka, Koshi*; Kimura, Toru*; Abdel-Rahman, H. M.*; Nguyen, J.-T.*; McDaniel, K. F.*; Kohlbrenner, W. E.*; Molla, A.*; Adachi, Motoyasu; Tamada, Taro; Kuroki, Ryota; et al.
Journal of Medicinal Chemistry, 52(23), p.7604 - 7617, 2009/07
Times Cited Count：19 Percentile：44.7(Chemistry, Medicinal)A series of HIV protease inhibitor based on the allophenylnorstatine structure with various P2' moieties were synthesized. Among these analogues, we discovered that a small allyl group would maintain potent enzyme inhibitory activity compared to that of the 
-methylbenzyl moiety in clinical candidate 1 (KNI-764, also known as JE-2147, AG-1776 or SM-319777). Introduction of an anilinic amino group to 2 (KNI-727) improved water-solubility and anti-HIV-1 activity. X-ray crystallographic analysis of 13k (KNI-1689) with a 
-methallyl group at P2' position revealed hydrophobic interactions with Ala28, Ile84, and Ile50' similar to that of 1. The presence of an additional methyl group on the allyl group in compound 13k significantly increased anti-HIV activity over 1, while providing a rational drug design for structural minimization and improving membrane permeability.
Ninomiya, Hiromasa; Akiba, Masato; Fujii, Tsuneyuki; Fujita, Takaaki; Fujiwara, Masami*; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Hosogane, Nobuyuki; Ikeda, Yoshitaka; Inoue, Nobuyuki; et al.
Journal of the Korean Physical Society, 49, p.S428 - S432, 2006/12
To contribute DEMO and ITER, the design to modify the present JT-60U into superconducting coil machine, named National Centralized Tokamak (NCT), is being progressed under nationwide collaborations in Japan. Mission, design and strategy of this NCT program is summarized.
Kikuchi, Mitsuru; Tamai, Hiroshi; Matsukawa, Makoto; Fujita, Takaaki; Takase, Yuichi*; Sakurai, Shinji; Kizu, Kaname; Tsuchiya, Katsuhiko; Kurita, Genichi; Morioka, Atsuhiko; et al.
Nuclear Fusion, 46(3), p.S29 - S38, 2006/03
Times Cited Count：13 Percentile：41.76(Physics, Fluids & Plasmas)The National Centralized Tokamak (NCT) facility program is a domestic research program for advanced tokamak research to succeed JT-60U incorporating Japanese university accomplishments. The mission of NCT is to establish high beta steady-state operation for DEMO and to contribute to ITER. The machine flexibility and mobility is pursued in aspect ratio and shape controllability, feedback control of resistive wall modes, wide current and pressure profile control capability for the demonstration of the high-b steady state.
Tsuchiya, Katsuhiko; Akiba, Masato; Azechi, Hiroshi*; Fujii, Tsuneyuki; Fujita, Takaaki; Fujiwara, Masami*; Hamamatsu, Kiyotaka; Hashizume, Hidetoshi*; Hayashi, Nobuhiko; Horiike, Hiroshi*; et al.
Fusion Engineering and Design, 81(8-14), p.1599 - 1605, 2006/02
Times Cited Count：1 Percentile：9.98(Nuclear Science & Technology)no abstracts in English
Enoeda, Mikio; Akiba, Masato; Tanaka, Satoru*; Shimizu, Akihiko*; Hasegawa, Akira*; Konishi, Satoshi*; Kimura, Akihiko*; Koyama, Akira*; Sagara, Akio*; Muroga, Takeo*
Fusion Engineering and Design, 81(1-7), p.415 - 424, 2006/02
Times Cited Count：62 Percentile：96.4(Nuclear Science & Technology)no abstracts in English
plasma operationTamai, Hiroshi; Akiba, Masato; Azechi, Hiroshi*; Fujita, Takaaki; Hamamatsu, Kiyotaka; Hashizume, Hidetoshi*; Hayashi, Nobuhiko; Horiike, Hiroshi*; Hosogane, Nobuyuki; Ichimura, Makoto*; et al.
Nuclear Fusion, 45(12), p.1676 - 1683, 2005/12
Times Cited Count：15 Percentile：45.53(Physics, Fluids & Plasmas)Design studies are shown on the National Centralized Tokamak facility. The machine design is carried out to investigate the capability for the flexibility in aspect ratio and shape controllability for the demonstration of the high-beta steady state operation with nation-wide collaboration, in parallel with ITER towards DEMO. Two designs are proposed and assessed with respect to the physics requirements such as confinement, stability, current drive, divertor, and energetic particle confinement. The operation range in the aspect ratio and the plasma shape is widely enhanced in consistent with the sufficient divertor pumping. Evaluations of the plasma performance towards the determination of machine design are presented.
Enoeda, Mikio; Akiba, Masato; Tanaka, Satoru*; Shimizu, Akihiko*; Hasegawa, Akira*; Konishi, Satoshi*; Kimura, Akihiko*; Koyama, Akira*; Sagara, Akio*; Muroga, Takeo*
Fusion Science and Technology, 47(4), p.1023 - 1030, 2005/05
Times Cited Count：4 Percentile：30.51(Nuclear Science & Technology)The Fusion Council of Japan has established the long-term research and development program of the blanket in 1999. In the program, the solid breeder blanket was selected as the primary candidate blanket of the fusion power demonstration plant in Japan. In the program, Japan Atomic Energy Research Institute (JAERI) has been nominated as a leading institute of the development of solid breeder blankets, in collaboration with universities, for the near term power demonstration plant, while, universities including National Institute for Fusion Science (NIFS) are assigned mainly to develop advanced blankets for longer term power plant development. In the long term research and development program, ITER blanket module testing is identified as the most important milestone, by which integrity of candidate blanket concepts and structures are evaluated. In Japan, universities, NIFS and JAERI cover a variety of types of blanket development. This paper presents a plan and strategy for ITER blanket module testing in Japan.
Cd using liquid scintillation counterIto, Chihiro; Tanaka, Yasuyuki; Kurosawa, Kiyoko*; Motoki, Yoshiaki*; Do, V. K.; Furuse, Takahiro
no journal, ,
In this presentation, an HCl-free analytical method for Cd in aqueous solution samples containing multiple radionuclides by liquid scintillation counting is reported. We aimed to develop a chemical separation procedure of Cd from co-existing nuclides such as 
Co and/or 
Fe, which interfere with the beta-counting. The use of hydrochloric acid (HCl) was avoided to prevent facilities from corrosion. Accordingly, after a sample-matrix separation with a chelating disk, Cd was adsorbed on a cation exchange resin and then selectively eluted by sodium thiosulfate (Na
SO
), which has a high affinity for Cd. This developed method allowed the separation and purification of Cd from the sample matrix without the use of halogen acids.
U using ICP-MS/MSTanaka, Yasuyuki; Do, V. K.; Motoki, Yoshiaki*; Ota, Yuki; Iwahashi, Hiroyuki; Kurosawa, Kiyoko*; Furuse, Takahiro
no journal, ,
We examined the measurement method of U using triple-quadrupole inductively coupled plasma-mass spectrometry (ICP-MS/MS, Agilent 8900). The measurable mass to charge ratio (m/z) is expanded up to 275, the device can measure U
OO (m/z = 268) generated by the reaction with O, which was used as a reaction gas. This mass shift mode decreased the interference from hydride of 
U compared to the previously reported analytical method, which improved limit of detection of U using ICP-MS/MS. In this presentation, the optimized measurement condition of U measured at m/z = 268 by ICP-MS/MS is reported.
