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Journal Articles

PSTEP: Project for solar-terrestrial environment prediction

Kusano, Kanya*; Ichimoto, Kiyoshi*; Ishii, Mamoru*; Miyoshi, Yoshizumi*; Yoden, Shigeo*; Akiyoshi, Hideharu*; Asai, Ayumi*; Ebihara, Yusuke*; Fujiwara, Hitoshi*; Goto, Tadanori*; et al.

Earth, Planets and Space (Internet), 73(1), p.159_1 - 159_29, 2021/12

 Times Cited Count:6 Percentile:51.19(Geosciences, Multidisciplinary)

The PSTEP is a nationwide research collaboration in Japan and was conducted from April 2015 to March 2020, supported by a Grant-in-Aid for Scientific Research on Innovative Areas from the Ministry of Education, Culture, Sports, Science and Technology of Japan. It has made a significant progress in space weather research and operational forecasts, publishing over 500 refereed journal papers and organizing four international symposiums, various workshops and seminars, and summer school for graduate students at Rikubetsu in 2017. This paper is a summary report of the PSTEP and describes the major research achievements it produced.

Journal Articles

Analysis of $$n$$ + $$^6$$Li reactions using the continuum-discretized coupled-channels method

Ichinkhorloo, D.*; Matsumoto, Takuma*; Hirabayashi, Yoshiharu*; Kato, Kiyoshi*; Chiba, Satoshi

Journal of Nuclear Science and Technology, 48(11), p.1357 - 1360, 2011/10

 Times Cited Count:6 Percentile:44.28(Nuclear Science & Technology)

The $$n$$ + $$^6$$Li reactions are important not only from the basic interest of the system but also from the application point of view. In this work, we study $$^6$$Li breakup reactions of incident neutron energies 11.5, 14.1 and 18.0 MeV by applying an $$alpha$$ + $$d$$ cluster model to $$^{6}$$Li and using the continuum-discretized coupled-channels approach. At the present energy, our calculation gives almost good agreement with experimental data.

Journal Articles

Systematic description of the $$^6$$Li($$n,n'$$)$$^6$$Li$$^* to d+ alpha$$ reactions with the microscopic coupled-channels method

Matsumoto, Takuma*; Ichinkhorloo, D.*; Hirabayashi, Yoshiharu*; Kato, Kiyoshi*; Chiba, Satoshi

Physical Review C, 83(6), p.064611_1 - 064611_6, 2011/06

 Times Cited Count:21 Percentile:75.6(Physics, Nuclear)

We investigate $$^6$$Li($$n,n'$$)$$^6$$Li$$^* to d + alpha$$ reactions by using the continuum-discretized coupled-channels method with the complex Jeukenne-Lejeune-Mahaux effective nucleon-nucleon interaction. In this study, the $$^6$$Li nucleus is described by a d + $$alpha$$ cluster model. The calculated elastic cross sections for incident energies between 7.47 and 24.0 MeV are in good agreement with experimental data. Furthermore, we show that the neutron spectra for $$^6$$Li breakup states measured at selected angular points and incident energies can be also reproduced systematically.

Journal Articles

Establishment of neutron fluence monitoring techniques for quasi-monoenergetic neutron calibration fields of high energy at TIARA

Shikaze, Yoshiaki; Tanimura, Yoshihiko; Saegusa, Jun; Tsutsumi, Masahiro; Uchida, Yoshiaki*; Yoshizawa, Michio; Harano, Hideki*; Matsumoto, Tetsuro*; Mizuhashi, Kiyoshi

JAEA-Review 2010-065, JAEA Takasaki Annual Report 2009, P. 158, 2011/01

no abstracts in English

Journal Articles

Design progress of the ITER blanket remote handling equipment

Nakahira, Masataka; Matsumoto, Yasuhiro; Kakudate, Satoshi; Takeda, Nobukazu; Shibanuma, Kiyoshi; Tesini, A.*

Fusion Engineering and Design, 84(7-11), p.1394 - 1398, 2009/06

 Times Cited Count:20 Percentile:77.78(Nuclear Science & Technology)

Invessel components of ITER have to be maintained by remote handling (RH) equipment due to high radiation level in the vacuum vessel (VV) after D-D operation. Blanket module (BM) is maintained by a manipulator mounted on a vehicle traveled through an articulated rail deployed inside the VV. Towards the construction, the BLRH equipment design has been improved and developed in more detail. The overview of design results are introduced in this paper. The design of rail deployment system of the BLRH has been updated to enable the rail connection in the transfer cask in order to minimize occupation space. For this purpose, design works have been performed for concept, sequence and typical simulation of BL replacement in the VV and rail deployment of the RH equipment in the cask, including cask docking. The technical issues of the rail connection in the cask are (1) tight tolerance of a pin at a hinge, (2) limited space of the connection inside a cask and (3) tight positioning accuracy. This paper summarizes the idea to solve these issues and a result of the design work. The paper also introduces a new cable handling equipment, rail support equipment and BL receiver/transporter.

Journal Articles

Mock-up test on key components of ITER blanket remote handling system

Takeda, Nobukazu; Kakudate, Satoshi; Nakahira, Masataka; Matsumoto, Yasuhiro; Taguchi, Ko; Kozaka, Hiroshi; Shibanuma, Kiyoshi; Tesini, A.*

Fusion Engineering and Design, 84(7-11), p.1813 - 1817, 2009/06

 Times Cited Count:11 Percentile:59.85(Nuclear Science & Technology)

The maintenance operation of the ITER in-vessel component, such as a blanket and divertor, must be executed by the remote equipment because of the high $$gamma$$-ray environment. During the Engineering Design Activity (EDA), the Japan Atomic Energy Agency had been fabricated the prototype of the vehicle manipulator system for the blanket remote handling and confirmed feasibility of this system including automatic positioning of the blanket and rail deployment procedure of the articulated rail. The JAEA is continuing several R&Ds so that the system can be procured smoothly to ITER. The residual key issues after the EDA are rail connection, cable handling and in-situ replacement of first wall. The last issue is newly raised and currently under the discussion. This presentation concentrates on the former two issues.

Journal Articles

Progress of R&D and design of blanket remote handling equipment for ITER

Kakudate, Satoshi; Takeda, Nobukazu; Nakahira, Masataka; Matsumoto, Yasuhiro; Shibanuma, Kiyoshi; Tesini, A.*

Fusion Engineering and Design, 83(10-12), p.1850 - 1855, 2008/12

 Times Cited Count:13 Percentile:64.63(Nuclear Science & Technology)

The design of in-vessel transporter (IVT) including vehicle manipulator has been updated according to the design changes such as blanket segmentation and structure, taking account of the interface between modules and vehicle manipulator. In particular, the updated design of the vehicle manipulator and rail has been carried out in order to avoid the interference between modules and vehicle manipulator. According to the updated design, the vehicle manipulator has been reduced by about 30%, compared with the reference design. In parallel with design activities, the R&D to clarify the specifications of the IVT design in detail is also performed, i.e., simulation system to provide the visual information during maintenance, dry lubricant to prevent the lubricant oil from spreading in the VV. The rail connection and cable handling in the transfer cask, which are critical issues for IVT system, are under preparation of the demonstration tests to finalize the design of the IVT system. Connection of the rail joint and cable handling test facilities are planned and under fabrication now. These test facility will be installed by the end of March 2008, and the performance tests will be carried out from April 2008.

Journal Articles

Free radical scavenger edaravone suppresses X-ray-induced apoptosis through p53 inhibition in MOLT-4 cells

Sasano, Nakashi*; Enomoto, Atsushi*; Hosoi, Yoshio*; Katsumura, Yosuke; Matsumoto, Yoshihisa*; Shiraishi, Kenshiro*; Miyagawa, Kiyoshi*; Igaki, Hiroshi*; Nakagawa, Keiichi*

Journal of Radiation Research, 48(6), p.495 - 503, 2007/11

 Times Cited Count:21 Percentile:53.82(Biology)

Journal Articles

Study of long-term behavior of engineered and geological barrier system

Aoyanagi, Shigeo; Oda, Yoshihiro; Sasamoto, Hiroshi; Shibata, Masahiro; Tanai, Kenji; Taniguchi, Naoki; Nishimura, Mayuka; Fujisaki, Kiyoshi; Kikuchi, Hirohito*; Matsumoto, Kazuhiro*

Hoshasei Haikibutsu Anzen Kenkyu Nenji Keikaku (Heisei-13-Nendo$$sim$$Heisei-17-Nendo) Kenkyu Seika Hokokushu, p.179 - 203, 2006/03

no abstracts in English

Journal Articles

Remote handling systems for ITER

Honda, Tsutomu*; Hattori, Yukiya*; Holloway, C.*; Martin, E.*; Matsumoto, Yasuhiro*; Matsunobu, Takashi*; Suzuki, Toshiyuki*; Tesini, A.*; Baulo, V.*; Haange, R.*; et al.

Fusion Engineering and Design, 63-64, p.507 - 518, 2002/12

 Times Cited Count:16 Percentile:69.83(Nuclear Science & Technology)

The requirement to reduce the construction cost for ITER as compared with the 1998 ITER design, has led to a reduction in the size of the ITER machine and a number of design changes which have an impact on the remote maintenance of ITER. Major components to be considered for remote handling (RH) include the divertor cassettes, shield blanket modules, neutral beamline components, as well as in-port components, which are integrated with the port shield plug such as auxiliary heating equipment, limiters and test blanket modules. The design of the following equipment has been adapted for the smaller machine with reduced access space for the RH equipment: the RH equipment used for the in-vessel RH operationsto be deployed from the casks, the RH equipment that is used to remove the in-port assemblies (port plugs), as well as the remotely operated casks, which can be attached to and removed from vacuum vessel ports by using double -door systems. Defective components are loaded in transfer casks and moved to the hot cell facility by means of a remotely-operated air floatation system attached underneath the cask, where they dock against identical port interfaces and unload the component for remote refurbishment and/or waste storage.

Journal Articles

Status of extened performance tests for blanket remote maintenance in the ITER L6 project

Kakudate, Satoshi; Oka, Kiyoshi; Yoshimi, Takashi*; Hiyama, Masayuki; Taguchi, Ko*; Shibanuma, Kiyoshi; Koizumi, Koichi; Matsumoto, Yasuhiro*; Honda, Tsutomu*; Haange, R.*

Nuclear Fusion, 42(3), p.243 - 246, 2002/03

 Times Cited Count:3 Percentile:10.69(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

ITER engineering design

Shimomura, Yasuo; Tsunematsu, Toshihide; Yamamoto, Shin; Maruyama, So; Mizoguchi, Tadanori*; Takahashi, Yoshikazu; Yoshida, Kiyoshi; Kitamura, Kazunori*; Ioki, Kimihiro*; Inoue, Takashi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 78(Suppl.), 224 Pages, 2002/01

no abstracts in English

Journal Articles

Mechanical characteristics and position control of vehicle/manipulator for ITER blanket remote maintenance

Kakudate, Satoshi; Oka, Kiyoshi; Yoshimi, Takashi*; Taguchi, Ko*; Nakahira, Masataka; Takeda, Nobukazu; Shibanuma, Kiyoshi; Obara, Kenjiro; Tada, Eisuke; Matsumoto, Yasuhiro*; et al.

Fusion Engineering and Design, 51-52(1-4), p.993 - 999, 2000/11

 Times Cited Count:9 Percentile:54.14(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Burnup code for fuel assembly by Monte Carlo code; MKENO-BURN

Naito, Yoshitaka; Suyama, Kenya; Masukawa, Fumihiro; Matsumoto, Kiyoshi; Kurosawa, Masayoshi; *

JAERI-Data/Code 96-037, 70 Pages, 1996/12

JAERI-Data-Code-96-037.pdf:1.68MB

no abstracts in English

Journal Articles

Failure probability evaluation of condensate water storage tank for seismic probabilistic safety assessment of nuclear power plant

*; Matsumoto, Kiyoshi; Hoshina, Hirofumi*

PSA95: Proc. of Probabilistic Safety Assessment Methodology and Applications, 2, p.735 - 740, 1995/00

no abstracts in English

Journal Articles

Seismic capacity evaluation of emergency diesel generator system

Matsumoto, Kiyoshi; Muramatsu, Ken; *; *

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering, Vol. 3, 0, p.1385 - 1392, 1995/00

no abstracts in English

Journal Articles

Development of seismic PSA methodology at JAERI

Muramatsu, Ken; ; Matsumoto, Kiyoshi; ; Kondo, Masaaki; *

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering, Vol. 3, 0, p.1333 - 1340, 1995/00

no abstracts in English

Journal Articles

Seismic probabilistic safety assessment of nuclear power plants

Matsumoto, Kiyoshi; Muramatsu, Ken

Denshi Joho Tsushin Gakkai Gijutsu Kenkyu Hokoku, 92(51), p.33 - 37, 1993/02

no abstracts in English

Journal Articles

Development of method to determine instability threshold with RETRAN code

Araya, Fumimasa; Hirano, Masashi; ; Matsumoto, Kiyoshi; Yokobayashi, Masao; Kosaka, Atsuo

Nihon Genshiryoku Gakkai-Shi, 34(9), p.879 - 888, 1992/09

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of LaSalle-2 neutron flux oscillation event with RETRAN code

Araya, Fumimasa; Hirano, Masashi; ; Matsumoto, Kiyoshi; Yokobayashi, Masao; Kosaka, Atsuo

Nihon Genshiryoku Gakkai-Shi, 34(6), p.565 - 575, 1992/06

 Times Cited Count:1 Percentile:17.26(Nuclear Science & Technology)

no abstracts in English

40 (Records 1-20 displayed on this page)