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Journal Articles

Current ramps in tokamaks; From present experiments to ITER scenarios

Imbeaux, F.*; Citrin, J.*; Hobirk, J.*; Hogeweij, G. M. D.*; K$"o$chl, F.*; Leonov, V. M.*; Miyamoto, Seiji; Nakamura, Yukiharu*; Parail, V.*; Pereverzev, G. V.*; et al.

Nuclear Fusion, 51(8), p.083026_1 - 083026_11, 2011/08

 Times Cited Count:35 Percentile:80.68(Physics, Fluids & Plasmas)

Journal Articles

Current ramps in tokamaks; From present experiments to ITER scenarios

Imbeaux, F.*; Basiuk, V.*; Budny, R.*; Casper, T.*; Citrin, J.*; Fereira, J.*; Fukuyama, Atsushi*; Garcia, J.*; Gribov, Y. V.*; Hayashi, Nobuhiko; et al.

Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2011/03

Journal Articles

Electronic structure of U(Ru$$_{1-x}$$Rh$$_{x}$$)$$_2$$Si$$_2$$ studied by laser angle-resolved photoemission spectroscopy

Yoshida, Rikiya*; Nakamura, Yoshiaki*; Fukui, Masaki*; Haga, Yoshinori; Yamamoto, Etsuji; Onuki, Yoshichika; Okawa, Mario*; Shin, S.*; Hirai, Masaaki*; Muraoka, Yuji*; et al.

Journal of Physics; Conference Series, 273, p.012021_1 - 012021_4, 2011/02

 Times Cited Count:1 Percentile:34.07

Journal Articles

Signature of hidden order and evidence for periodicity modification in URu$$_2$$Si$$_2$$

Yoshida, Rikiya*; Nakamura, Yoshiaki*; Fukui, Masaki*; Haga, Yoshinori; Yamamoto, Etsuji; Onuki, Yoshichika; Okawa, Mario*; Shin, S.*; Hirai, Masaaki*; Muraoka, Yuji*; et al.

Physical Review B, 82(20), p.205108_1 - 205108_6, 2010/11

 Times Cited Count:61 Percentile:88.17(Materials Science, Multidisciplinary)

Journal Articles

Current ramps in tokamaks; From present experiments to ITER scenarios

Imbeaux, F.*; Basiuk, V.*; Budny, R.*; Casper, T.*; Citrin, J.*; Fereira, J.*; Fukuyama, Atsushi*; Garcia, J.*; Gribov, Y. V.*; Hayashi, Nobuhiko; et al.

Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2010/10

In order to prepare adequate current ramp-up and ramp-down scenarios for ITER, present experiments from several tokamaks have been analyzed by means of integrated modeling in view of determining relevant heat transport models for these operation phases. The results of these studies are presented and projections to ITER current ramp-up and ramp-down scenarios are done, focusing on the baseline inductive scenario (main heating plateau current of 15 MA). Various transport models have been tested by means of integrated modeling against experimental data from ASDEX Upgrade, C-Mod, DIII-D, JET and Tore Supra, including both Ohmic plasmas and discharges with additional heating/current drive. With using the most successful models, projections to the ITER current ramp-up and ramp-down phases are carried out. Though significant differences between models appear on the electron temperature prediction, the final q-profiles reached in the simulation are rather close.

JAEA Reports

Development of overpack database

Taniguchi, Naoki; Nakamura, Ario*

JAEA-Data/Code 2009-022, 56 Pages, 2010/03

JAEA-Data-Code-2009-022.pdf:14.6MB

In geological disposal of high-level radioactive waste, overpack is required to prevent vitrified waste from the contacting groundwater with during a certain period of time. At present, the period is defined as 1000 years for complete containment and developments of technologies for design, manufacturing and quality assurance and researches for improving long-term performance have been carried out. Each R&D results have been published as a reports or journal papers by each individual institute. However, it is necessary to integrate these results so as to develop a practical knowledge base that would be useful for design of an overpack for a specific repository site, establishment of the codes and standards or other general purposes. Accordingly, we have been developing a database, which integrate R&D results on design concepts of overpack, technologies for design and manufactureing, test data of the characteristics as an overpack and so on. The basic structure of the database has already been completed last year. At present, two main data; corrosion data and the test data of overpack welding and inspections, are being summarized and imported into the database system. In this report, contents of the table were discussed and the datasets that have already been imported into the database system were appended.

JAEA Reports

Development of basic structure for overpack database

Taniguchi, Naoki; Nakamura, Ario*

JAEA-Data/Code 2008-032, 13 Pages, 2009/03

JAEA-Data-Code-2008-032.pdf:1.56MB

In geological disposal of high-level radioactive waste, overpack is required to prevent vitrified waste from the contacting groundwater with during a certain period of time. At present, the period is defined as 1000 years for complete containment and developments of technologies for design, manufacturing and quality assurance and researches for improving long-term performance have been carried out. Each R&D results have been published as a reports or journal papers by each individual institute. However, it is necessary to integrate these results so as to develop a practical knowledge base that would be useful for design of an overpack for a specific repository site, establishment of the codes and standards or other general purposes. Accordingly, we have been developing a database, which integrate R&D results on design concepts of overpack, technologies for design and manufacturing, test data of the characteristics as an overpack and so on. This report presents a current status of the overpack database using a commercial application software basic structure and an example of a menu for the database.

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