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At]NaAt and [
I]NaI in an NIS-expressing thyroid cancer mouse modelWatabe, Tadashi*; Liu, Y.*; Kaneda, Kazuko*; Sato, Tatsuhiko; Shirakami, Yoshifumi*; Oe, Kazuhiro*; Toyoshima, Atsushi*; Shimosegawa, Eku*; Wang, Y.*; Haba, Hiromitsu*; et al.
International Journal of Molecular Sciences (Internet), 23(16), p.9434_1 - 9434_11, 2022/08
Times Cited Count：7 Percentile：78.48(Biochemistry & Molecular Biology)In this study, we compare the therapeutic effect between [At]NaAt and [I]NaI. In vitro analysis of double-stranded DNA break (DSB) and colony formation assay were performed using K1-NIS cells. [At]NaAt induced higher numbers of DSBs and had a reduced colony formation than [I]NaI. In K1-NIS mice, dose-dependent therapeutic effects were observed in both [At]NaAt and [I]NaI. The superior therapeutic effect of [At]NaAt suggests the promising clinical applicability of targeted alpha therapy using [At]NaAt in patients with differentiated thyroid cancer refractory to standard [I]NaI treatment.
Togashi, Tadashi*; Takahashi, Eiji*; Midorikawa, Katsumi*; Aoyama, Makoto; Yamakawa, Koichi; Sato, Takahiro*; Iwasaki, Atsushi*; Owada, Shigeki*; Okino, Tomoya*; Yamanouchi, Kaoru*; et al.
Optics Express (Internet), 19(1), p.317 - 324, 2011/01
Times Cited Count：96 Percentile：96.45(Optics)The 13th harmonic of a Ti:sapphire (Ti:S) laser in the plateau region was injected as a seeding source to a 250-MeV free-electron-laser (FEL) amplifier. When the amplification conditions were fulfilled, strong enhancement of the radiation intensity by a factor of 650 was observed. The random and uncontrollable spikes, which appeared in the spectra of the Self-Amplified Spontaneous Emission (SASE) based FEL radiation without the seeding source, were found to be suppressed drastically to form to a narrow-band, single peak profile at 61.2 nm. The properties of the seeded FEL radiation were well reproduced by numerical simulations. We discuss the future precept of the seeded FEL scheme to the shorter wavelength region.
Wei, G.; Koseki, Tadashi*; Igarashi, Susumu*; Tomizawa, Masahito*; Takano, Jumpei*; Ishii, Koji*; Shirakata, Masashi*; Fan, K.*; Hatakeyama, Shuichiro; Uota, Masahiko*; et al.
Proceedings of 1st International Particle Accelerator Conference (IPAC '10) (Internet), p.3915 - 3917, 2010/05
Wei, G.; Koseki, Tadashi*; Tomizawa, Masahito*; Igarashi, Susumu*; Ishii, Koji*; Ando, Ainosuke; Takano, Jumpei*; Uota, Masahiko*; Fan, K.*; Hatakeyama, Shuichiro; et al.
Proceedings of 1st International Particle Accelerator Conference (IPAC '10) (Internet), p.3918 - 3920, 2010/05
Honda, Atsushi; Okano, Fuminori; Oshima, Katsumi; Akino, Noboru; Kikuchi, Katsumi; Tanai, Yutaka; Takenouchi, Tadashi; Numazawa, Susumu*; Ikeda, Yoshitaka
Fusion Engineering and Design, 83(2-3), p.276 - 279, 2008/04
Times Cited Count：11 Percentile：59.16(Nuclear Science & Technology)The control system of the cryogenic facility in the JT-60 NBI system has been renewed by employing the PLC (Programmable Logic Controller) and SCADA (Supervisory Control And Data Acquisition) system. The original control system was constructed about 20 years ago by specifying the DCS (Distributed Control System) computer to deal with 400 feedback loops. Recently, troubles on this control system have increased due to its aged deterioration. To maintain a high reliability of the cryogenic facility, a new control system has been intended with PLC and SCADA system. By optimizing the function blocks and connecting them in the FBD language, the feedback loops in the new control system have been successfully replaced from DCS to PLC without software developer. At present, the new control system has worked well. This is the first application of the marketable PLC to the actual system with feedback loops of 
400 produced by the user itself.
Ikeda, Yoshitaka; Akino, Noboru; Ebisawa, Noboru; Hanada, Masaya; Inoue, Takashi; Honda, Atsushi; Kamada, Masaki; Kawai, Mikito; Kazawa, Minoru; Kikuchi, Katsumi; et al.
Fusion Engineering and Design, 82(5-14), p.791 - 797, 2007/10
Times Cited Count：22 Percentile：80.64(Nuclear Science & Technology)Modification of JT-60U to a superconducting device (so called JT-60SA) has been planned to contribute to ITER and DEMO. The NBI system is required to inject 34 MW for 100 s. The upgraded NBI system consists of twelve positive ion based NBI (P-NBI) units and one negative ion based NBI (N-NBI) unit. The injection power of the P-NBI units are 2 MW each at 85 keV, and the N-NBI unit will be 10 MW at 500 keV, respectively. On JT-60U, the long pulse operation of 30 s at 2 MW (85 keV) and 20 s at 3.2 MW (320 keV) have been achieved on P-NBI and N-NBI units, respectively. Since the temperature increase of the cooling water in both ion sources is saturated within 20 s, further pulse extension up to 100 s is expected to mainly modify the power supply systems in addition to modification of the N-NBI ion source for high acceleration voltage. The detailed technical design of the NBI system for JT-60SA is presented.
Ikeda, Yoshitaka; Umeda, Naotaka; Akino, Noboru; Ebisawa, Noboru; Grisham, L. R.*; Hanada, Masaya; Honda, Atsushi; Inoue, Takashi; Kawai, Mikito; Kazawa, Minoru; et al.
Nuclear Fusion, 46(6), p.S211 - S219, 2006/06
Times Cited Count：59 Percentile：87.2(Physics, Fluids & Plasmas)Recently, the extension of the pulse duration up to 30 sec has been intended to study quasi-steady state plasma on JT-60U N-NBI system. The most serious issue is to reduce the heat load on the grids for long pulse operation. Two modifications have been proposed to reduce the heat load. One is to suppress the beam spread which may be caused by beamlet-beamlet interaction in the multi-aperture grid due to the space charge force. Thin plates were attached on the extraction grid to modify the local electric field. The plate thickness was optimized to steer the beamlet deflection. The other is to reduce the stripping loss, where the electron of the negative ion beam is stripped and accelerated in the ion source and then collides with the grids. The ion source was modified to reduce the pressure in the accelerator column to suppress the beam-ion stripping loss. Up to now, long pulse injection of 17 sec for 1.6 MW and 25 sec for 
1 MW has been obtained by one ion source with these modifications.
Honda, Atsushi; Okano, Fuminori; Oshima, Katsumi; Akino, Noboru; Kikuchi, Katsumi; Tanai, Yutaka; Takenouchi, Tadashi; Numazawa, Susumu*
JAEA-Technology 2006-020, 20 Pages, 2006/03
JAEA-Technology-2006-020.pdf:2.96MB
no abstracts in English
Kikuchi, Katsumi*; Akino, Noboru; Ikeda, Yoshitaka; Oga, Tokumichi; Oshima, Katsumi*; Okano, Fuminori; Takenouchi, Tadashi*; Tanai, Yutaka*; Honda, Atsushi
Heisei-16-Nendo Osaka Daigaku Sogo Gijutsu Kenkyukai Hokokushu (CD-ROM), 4 Pages, 2005/03
no abstracts in English
Maruyama, Yoichiro; Kubomura, Hiroyuki*; Kasamatsu, Tadashi*; Matsuoka, Shinichi*; Nakano, Fumihiko*; Kan, Hirofumi*
JAERI-Tech 2004-056, 14 Pages, 2004/09
JAERI-Tech-2004-056.pdf:3.49MB
A high average power tunable solid state laser is pumped by the second harmonic of LD-pumped high repetition rate Nd:YAG laser consisting of a single-longitudinal-mode oscillator and amplifiers. To operate the Nd:YAG laser oscillator with a single-longitudinal-mode by injection seeding, the cavity length control is required to coincide the resonant frequency of Nd:YAG laser oscillator with the frequency of seeder. For this purpose, a cavity length control system of the Nd:YAG laser oscillator is developed and the characteristics are studied. With this system, the cavity length is controlled at the pulse repetition rate of 0.5 kHz and the single frequency operation for more than three hours is realized.
Konomura, Mamoru; Ogawa, Takashi; Okano, Yasushi; Yamaguchi, Hiroyuki; Murakami, Tsutomu; Takaki, Naoyuki; Nishiguchi, Youhei; Sugino, Kazuteru; Naganuma, Masayuki; Hishida, Masahiko; et al.
JNC TN9400 2004-035, 2071 Pages, 2004/06
JNC-TN9400-2004-035.pdf:76.42MB
The attractive concepts for Sodium-, lead-bismuth-, helium- and water-cooled FBRs have been created through using typical plant features and employing advanced technologies. Efforts on evaluating technological prospects of feasibility have been paid for these concepts. Also, it was comfirmed if these concepts satisfy design requierments of capability and performance presumed in the feasibilty study on commertialization of Fast Breeder Reactor Systems. As results, it was concluded that the selection of sodium-cooled reactor was most rational for practical use of FBR technologies in 2015.
Takano, Hitoshi*; Sugimoto, Yoshihiro*; Yamashita, Tadashi*; Yamada, Naoyuki*
JNC TJ6420 2003-011, 127 Pages, 2003/02
JNC-TJ6420-2003-011.pdf:4.56MB
Drilling and high resolution electrical survey was carried out to make a geological structure model around mill tailing yard. Following by drill investigation, Distribution of the granite which became fragility was confirmed by the development of fractures with hydrothermal vein. However, fresh bedrock is distributed deeper than 40m. Permeability of weathering granite is about in 1.15
10
m/sec. The value agrees previous findings. In fresh granite, permeability is 4.3310
m/sec, and it value is larger than existing data. It is for developing of fractures in fresh granite. At high resolution electrical survey, analysis is done by 3 dimensions. By analyzing it with 3 dimensions, good resistivity distribution was provided. From resistivity distribution, tailing, weathered granite or sedimentary rock and fresh granite are classified. Resistivity distribution was taken out from lines or seismic exploration refraction method, and compared between two methods. As a result, low resistivity region is fitted low velocity zone and high resistivity region is fitted high velocity zone. Topography and 4 geological models are created. These models are output as versatile text data to show relation of a coordinate and the point of contact.
Shibata, Keiichi; Kawano, Toshihiko*; Nakagawa, Tsuneo; Iwamoto, Osamu; Katakura, Junichi; Fukahori, Tokio; Chiba, Satoshi; Hasegawa, Akira; Murata, Toru*; Matsunobu, Hiroyuki*; et al.
Journal of Nuclear Science and Technology, 39(11), p.1125 - 1136, 2002/11
Times Cited Count：669 Percentile：96.97(Nuclear Science & Technology)Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various benchmark tests of the previous library JENDL-3.2. The major problems of the JENDL-3.2 data were solved by the new library: overestimation of criticality values for thermal fission reactors was improved by the modifications of fission cross sections and fission neutron spectra for 
U; incorrect energy distributions of secondary neutrons from important heavy nuclides were replaced with statistical model calculations; the inconsistency between elemental and isotopic evaluations was removed for medium-heavy nuclides. Moreover, covariance data were provided for 20 nuclides. The reliability of JENDL-3.3 was investigated by the benchmark analyses on reactor and shielding performances. The results of the analyses indicate that JENDL-3.3 predicts various reactor and shielding characteristics better than JENDL-3.2.
Takahashi, Hiroki; Kano, Tadashi*; Takahashi, Teruo*; Kyoya, Masahiko; Shimazaki, Junya*
JAERI-Tech 2001-068, 78 Pages, 2001/10
JAERI-Tech-2001-068.pdf:82.36MB
JAERI had carried out design study about a lightweight and compact integral type reactor (an advanced marine reactor) with passive safety equipment, and completed an engineering design. To confirm the design performance and operation performance and to utilize the study of automation of the reactor operation, we have developed a simulator for the integral type reactor. This can be used also for research and development of a small reactor.However, in using for research and development, the improvement in a performance of hardware and a human machine interface of software of the simulator were needed. Renewal of hardware and improvement of software have been conducted. Thereby, the operability of an integral-reactor simulator has been improved. Moreover, versatility, maintainability, extendibility, and the improvement of system performed by using the conventional hardware and software.This is a report on hardware renewal and the interface improvement of the integral type reactor simulator mainly focused on contents of the enhancement in a human machine interface.
PO
at 3GPaSaito, Takashi*; Terashima, Takashi*; Azuma, Masaki*; Takano, Mikio*; Goto, Tadashi*; Ota, Hiroshi*; Utsumi, Wataru; Bordet, P.*; Johnston, D. C.*
Journal of Solid State Chemistry, 153(1), p.124 - 131, 2000/08
Times Cited Count：37 Percentile：79.52(Chemistry, Inorganic & Nuclear)no abstracts in English
Tasaka, Kanji; Katakura, Junichi; Ihara, Hitoshi; Yoshida, Tadashi*; Iijima, Shungo*; Nakashima, Ryuzo*; Nakagawa, Tsuneo; Takano, Hideki
JAERI 1320, 253 Pages, 1990/09
no abstracts in English
Asami, Tetsuo*; Iijima, Shungo*; ; Ihara, Hitoshi; Kawai, Masayoshi*; ; Komuro, Yuichi; Shibata, Keiichi; Takano, Hideki; *; et al.
Nihon Genshiryoku Gakkai-Shi, 31(11), p.1190 - 1217, 1989/11
no abstracts in English
Nakagawa, Tsuneo; Takano, Hideki; Yoshida, Tadashi*; Masukawa, Fumihiro; Iijima, Shungo*
Nihon Genshiryoku Gakkai-Shi, 31(10), p.1083 - 1092, 1989/10
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Yokoyama, Hiroomi*; Kanazawa, Toshio*; Fukuma, Tadashi*; Tamekiyo, Kozo*; Yanagida, Koji*; Furuya, Takashi*; Kono, Hiroshi*; Ito, Keiji*; Shirakura, Takao*; Kashiwara, Shinichiro*; et al.
PNC TN8410 87-086VOL2, 944 Pages, 1986/09
Yokoyama, Hiroomi*; Kanazawa, Toshio*; Fukuma, Tadashi*; Tamekiyo, Kozo*; Yanagida, Koji*; Furuya, Takashi*; Kono, Hiroshi*; Ito, Keiji*; Shirakura, Takao*; Kashiwara, Shinichiro*; et al.
PNC TN8410 87-086VOL1, 1037 Pages, 1986/09
PNC-TN8410-87-086VOL1.pdf:34.39MB
A detailed design for a New Material Nitric Acid Recovery Evaporator was carried out with a plan to use it to replace an already constructed stainless steel Nitric Acid Recovery Evaporator at the Power Reactor and Nuclear Fuel Development Corporation's Tokai Works. Most of the original Evaporator's conditions such as compliance with applicable laws, standards, structure, treatment performance and operating conditions were maintained when designing the new machine. The material is titanium with the addition of 5% tantalum. The Evaporator was designed with an operational life expectance of 10 years. We have calculated that the new Evaporator will have sufficient strength (including a seismatic design) and have the same evaporative performance as the already constructed one. During design, we referred to the results of already completed basic designs (Phase 1) of New Material Nitric Acid Recovery Evaporators, design and production of small-scale test equipment units, and the development of successful joints between different materials. We also considered manufacturing, installation, trial runs, maintenance, and the specifications for materials used for manufacturing, installation, piping and operation of the new Evaporator.
Wei, G.; Koseki, Tadashi; Igarashi, Susumu*; Takano, Jumpei*; Tomizawa, Masahito*
no journal, ,
