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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

Identified charged hadron production in $$p + p$$ collisions at $$sqrt{s}$$ = 200 and 62.4 GeV

Adare, A.*; Afanasiev, S.*; Aidala, C.*; Ajitanand, N. N.*; Akiba, Yasuyuki*; Al-Bataineh, H.*; Alexander, J.*; Aoki, Kazuya*; Aphecetche, L.*; Armendariz, R.*; et al.

Physical Review C, 83(6), p.064903_1 - 064903_29, 2011/06

 Times Cited Count:184 Percentile:99.44(Physics, Nuclear)

Transverse momentum distributions and yields for $$pi^{pm}, K^{pm}, p$$, and $$bar{p}$$ in $$p + p$$ collisions at $$sqrt{s}$$ = 200 and 62.4 GeV at midrapidity are measured by the PHENIX experiment at the RHIC. We present the inverse slope parameter, mean transverse momentum, and yield per unit rapidity at each energy, and compare them to other measurements at different $$sqrt{s}$$ collisions. We also present the scaling properties such as $$m_T$$ and $$x_T$$ scaling and discuss the mechanism of the particle production in $$p + p$$ collisions. The measured spectra are compared to next-to-leading order perturbative QCD calculations.

Journal Articles

Azimuthal correlations of electrons from heavy-flavor decay with hadrons in $$p+p$$ and Au+Au collisions at $$sqrt{s_{NN}}$$ = 200 GeV

Adare, A.*; Afanasiev, S.*; Aidala, C.*; Ajitanand, N. N.*; Akiba, Yasuyuki*; Al-Bataineh, H.*; Alexander, J.*; Aoki, Kazuya*; Aphecetche, L.*; Aramaki, Y.*; et al.

Physical Review C, 83(4), p.044912_1 - 044912_16, 2011/04

 Times Cited Count:8 Percentile:49.7(Physics, Nuclear)

Measurements of electrons from the decay of open-heavy-flavor mesons have shown that the yields are suppressed in Au+Au collisions compared to expectations from binary-scaled $$p+p$$ collisions. Here we extend these studies to two particle correlations where one particle is an electron from the decay of a heavy flavor meson and the other is a charged hadron from either the decay of the heavy meson or from jet fragmentation. These measurements provide more detailed information about the interaction between heavy quarks and the quark-gluon matter. We find the away-side-jet shape and yield to be modified in Au+Au collisions compared to $$p+p$$ collisions.

JAEA Reports

Conceptual design of the SlimCS fusion DEMO reactor

Tobita, Kenji; Nishio, Satoshi*; Enoeda, Mikio; Nakamura, Hirofumi; Hayashi, Takumi; Asakura, Nobuyuki; Uto, Hiroyasu; Tanigawa, Hiroyasu; Nishitani, Takeo; Isono, Takaaki; et al.

JAEA-Research 2010-019, 194 Pages, 2010/08

JAEA-Research-2010-019-01.pdf:48.47MB
JAEA-Research-2010-019-02.pdf:19.4MB

This report describes the results of the conceptual design study of the SlimCS fusion DEMO reactor aiming at demonstrating fusion power production in a plant scale and allowing to assess the economic prospects of a fusion power plant. The design study has focused on a compact and low aspect ratio tokamak reactor concept with a reduced-sized central solenoid, which is novel compared with previous tokamak reactor concept such as SSTR (Steady State Tokamak Reactor). The reactor has the main parameters of a major radius of 5.5 m, aspect ratio of 2.6, elongation of 2.0, normalized beta of 4.3, fusion out put of 2.95 GW and average neutron wall load of 3 MW/m$$^{2}$$. This report covers various aspects of design study including systemic design, physics design, torus configuration, blanket, superconducting magnet, maintenance and building, which were carried out increase the engineering feasibility of the concept.

Journal Articles

Compact DEMO, SlimCS; Design progress and issues

Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Kawashima, Hisato; Kurita, Genichi; Tanigawa, Hiroyasu; Nakamura, Hirofumi; Honda, Mitsuru; Saito, Ai*; Sato, Satoshi; et al.

Nuclear Fusion, 49(7), p.075029_1 - 075029_10, 2009/07

 Times Cited Count:137 Percentile:97.72(Physics, Fluids & Plasmas)

Recent design study on SlimCS focused mainly on the torus configuration including blanket, divertor, materials and maintenance scheme. For vertical stability of elongated plasma and high beta access, a sector-wide conducting shell is arranged in between replaceable and permanent blanket. The reactor adopts pressurized-water-cooled solid breeding blanket. Compared with the previous advanced concept with supercritical water, the design options satisfying tritium self-sufficiency are relatively scarce. Considered divertor technology and materials, an allowable heat load to the divertor plate should be 8 MW/m$$^{2}$$ or lower, which can be a critical constraint for determining a handling power of DEMO (a combination of alpha heating power and external input power for current drive).

Journal Articles

SlimCS; Compact low aspect ratio DEMO reactor with reduced-size central solenoid

Tobita, Kenji; Nishio, Satoshi; Sato, Masayasu; Sakurai, Shinji; Hayashi, Takao; Shibama, Yusuke; Isono, Takaaki; Enoeda, Mikio; Nakamura, Hirofumi; Sato, Satoshi; et al.

Nuclear Fusion, 47(8), p.892 - 899, 2007/08

 Times Cited Count:57 Percentile:86.6(Physics, Fluids & Plasmas)

The concept for a compact DEMO reactor named "SlimCS" is presented. Distinctive features of the concept is low aspect ratio ($$A$$ = 2.6) and use of a reduced-size center solenoid (CS) which has a function of plasma shaping rather than poloidal flux supply. The reduced-size CS enables us to introduce a thin toroidal field (TF) coil system which contributes to reducing the weight and construction cost of the reactor. SlimCS is as compact as advanced commercial reactor designs such as ARIES-RS and produces 1 GWe in spite of moderate requirements for plasma parameters. Merits of low-$$A$$, i.e. vertical stability for high elongation and high beta limit are responsible for such reasonable physics requirements.

Journal Articles

Development of continuous sintering equipment for MOX fuel fabrication

Kurita, Ichiro

Nihon Genshiryoku Gakkai-Shi, 48(3), p.155 - 156, 2006/03

no abstracts in English

Journal Articles

Development of continuous sintering equipment for MOX fuel fabrication

Yamada, Yoshikazu; Kurita, Ichiro; Suzuki, Kazunori; Shinada, Kenta; Kato, Mitsuaki*

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 5 Pages, 2005/10

None

Journal Articles

Advanced fusion technologies developed for JT-60 superconducting Tokamak

Sakasai, Akira; Ishida, Shinichi; Matsukawa, Makoto; Akino, Noboru; Ando, Toshinari*; Arai, Takashi; Ezato, Koichiro; Hamada, Kazuya; Ichige, Hisashi; Isono, Takaaki; et al.

Nuclear Fusion, 44(2), p.329 - 334, 2004/02

no abstracts in English

Journal Articles

Advanced fusion technologies developed for JT-60 superconducting Tokamak

Sakasai, Akira; Ishida, Shinichi; Matsukawa, Makoto; Akino, Noboru; Ando, Toshinari*; Arai, Takashi; Ezato, Koichiro; Hamada, Kazuya; Ichige, Hisashi; Isono, Takaaki; et al.

Nuclear Fusion, 44(2), p.329 - 334, 2004/02

 Times Cited Count:7 Percentile:22.95(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Development of fresh fuel packaging for ATR demonstration reactor

Kurita, Ichiro; Kurakami, Junichi

Proceedings of 10th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM '92), p.1397 - 1402, 1992/00

None

Oral presentation

Development of a sea transport system for MOX powder

Ouchi, Yuichiro; Tadokoro, Noboru; Kitamura, Takafumi; Yoshida, Sachimasa; Kurita, Ichiro

no journal, , 

The Japan Atomic Energy Agency (JAEA) is planning to procure uranium and plutonium mixed oxide (MOX) powder necessary for the prototype fast breeder reactor MONJU and experimental reactor JOYO from Rokkasho Reprocessing Plant (RRP), which is operated by the Japan Nuclear Fuel Limited (JNFL). When both reactors operate as planned, an annual quantity of MOX is estimated at two tons (600 kg of fissile Pu). JAEA has developed a sea transport system including a transport package, shipping containers, vehicles, a ship, and ports, etc., to safely and securely transport large amounts of MOX powder compliant with physical protection measures for Category I materials. This paper describes development of the transport package and shipping container, and will outline the sea transport plan.

Oral presentation

Post-excavation grouting technology applied at 500 m depth of the Mizunami Underground Research laboratory, 1; Outline of grouting to reduce groundwater inflow

Mikake, Shinichiro; Sato, Toshinori; Ikeda, Koki; Watanabe, Kazuhiko; Kobayashi, Shinji*; Tsuji, Masakuni*; Kusano, Takashi*; Kurita, Kazuaki*

no journal, , 

no abstracts in English

Oral presentation

Post-excavation grouting technology applied at 500 m depth of the Mizunami Underground Research Laboratory, 2; New design and water inflow prediction

Mikake, Shinichiro; Sato, Toshinori; Kobayashi, Shinji*; Tsuji, Masakuni*; Kurita, Kazuaki*; Eguchi, Keita*

no journal, , 

no abstracts in English

Oral presentation

Post-excavation grouting technology applied at 500 m depth of the Mizunami Underground Research Laboratory, 3; Results of grouting

Mikake, Shinichiro; Sato, Toshinori; Kurita, Kazuaki*; Kusano, Takashi*; Tsuji, Masakuni*; Kobayashi, Shinji*

no journal, , 

no abstracts in English

Oral presentation

Post-excavation grouting technology applied at 500 m depth of the Mizunami Underground Research Laboratory, 4; Evaluation of new technology and effectiveness of reducing water inflow

Mikake, Shinichiro; Sato, Toshinori; Tsuji, Masakuni*; Kobayashi, Shinji*; Eguchi, Keita*; Kurita, Kazuaki*

no journal, , 

no abstracts in English

Oral presentation

Mizunami Underground Research Laboratory Project, Development of Engineering Technology for Underground Construction; Results and Evaluation for Post-excavation Grouting

Mikake, Shinichiro; Ikeda, Koki; Watanabe, Kazuhiko; Shiba, Nobuyuki; Kadoguchi, Yoshiaki; Tsuji, Masakuni*; Kusano, Takashi*; Kurita, Kazuaki*

no journal, , 

no abstracts in English

17 (Records 1-17 displayed on this page)
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