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Journal Articles

Carbon transport and fuel retention in JT-60U with higher temperature operation based on postmortem analysis

Yoshida, Masafumi; Tanabe, Tetsuo*; Adachi, Ayumu*; Hayashi, Takao; Nakano, Tomohide; Fukumoto, Masakatsu; Yagyu, Junichi; Miyo, Yasuhiko; Masaki, Kei; Itami, Kiyoshi

Journal of Nuclear Materials, 438, p.S1261 - S1265, 2013/07

 Times Cited Count:6 Percentile:43.8(Materials Science, Multidisciplinary)

Fuel retention rates and carbon re-deposition rates in the plasma shadowed areas in JT-60U were measured. Distributions of the fuel retention as well as the carbon re-deposition in the whole in-vessel of a large tokamak were clarified for the first time in the world. The fuel retention in the plasma shadowed areas was about two times larger than that in the carbon re-deposited layers on the plasma facing surface, although the amount of the carbon re-deposited on the plasma shadowed areas were about a half of that on the plasma facing surface, because of relatively lower temperature in the shadow areas causing higher hydrogen saturation concentration in the carbon re-deposited layers. The total fuel retention rate in JT-60U, including previously measured for all plasma facing areas, was evaluated to be 1.3$$times$$10$$^{20}$$ H+Ds$$^{-1}$$, which was lower than that in other devices, due to probably to higher temperature operation in JT-60U.

Journal Articles

Investigation of carbon dust accumulation in the JT-60U tokamak vacuum vessel

Asakura, Nobuyuki; Hayashi, Takao; Ashikawa, Naoko*; Fukumoto, Masakatsu

Journal of Nuclear Materials, 438, p.S659 - S663, 2013/07

 Times Cited Count:6 Percentile:43.8(Materials Science, Multidisciplinary)

Dust generated by the plasma-wall interaction is a potential source of the tritium retention in a fusion reactor. Dust samples were collected at 3, 5 and 3 different toroidal locations of the first wall, divertor surface and exhaust route under the divertor, respectively. On the tile surface, large number of dust was found, in particular, at the inner divertor rather upper area of the deposition layers, where recycling neutrals are increased during discharges. On the other hand, significant amount of dust (20-50 times larger) was generally accumulated at the bottom divertor, in particular, the plasma-unexposed area (remote area). It was found that the poloidal distribution is relatively symmetrical in the toroidal direction within a factor of three. Recently, analysis of dust spatial and size distributions, and evaluation of fuel retention in dust have been progressed. The total amount of the hydrogen isotope contained in the dust was estimated.

Journal Articles

Characteristics of tungsten and carbon dusts in JT-60U and evaluation of hydrogen isotope retention

Ashikawa, Naoko*; Asakura, Nobuyuki; Fukumoto, Masakatsu; Hayashi, Takao; Ueda, Yoshio*; Muroga, Takeo*

Journal of Nuclear Materials, 438, p.S664 - S667, 2013/07

 Times Cited Count:9 Percentile:57.33(Materials Science, Multidisciplinary)

In this study, W concentrations of dusts at P-8 section and hydrogen isotope retentions in dusts are analyzed. Compositions of C including W material dusts were observed in JT-60U. For an enhanced resolution of the XPS measurement to analyze quantitatively the composition of the dust flakes, the new analysis using XPS with indium foil was done and showed that the dust flakes contains about less than 1% of tungsten in carbon. Compositions of tungsten-carbon mixed dusts at different poloidal positions are reported. Produced areas of dust including W is estimated on the outer doom wing by IMPGYRO code. Relative intensities at low temperature regions were smaller than bulk divertor target, which may be caused by the high baking/operation temperature. Amounts of retained Hydrogen/Deuterium in dust particles depend on internal defects and carbon composition of dusts.

Journal Articles

Wall-conditioning plasmas by ECRF heating in KSTAR

Itami, Kiyoshi; Hong, S.-H.*; Bae, Y.-S.*; Matsukawa, Makoto; Kim, W.-C.*; KSTAR Team*

Journal of Nuclear Materials, 438, p.S930 - S935, 2013/07

 Times Cited Count:13 Percentile:69.38(Materials Science, Multidisciplinary)

Journal Articles

Spatial characterization of a divertor in the presence of an X-point MARFE by collisional-radiative modeling and line profile calculations

Koubiti, M.*; Nakano, Tomohide; Marandet, Y.*; Mekkaoui, A.*; Mouret, L.*; Rosato, J.*; Stamm, R.*

Journal of Nuclear Materials, 438, p.S599 - S601, 2013/07

 Times Cited Count:4 Percentile:32.32(Materials Science, Multidisciplinary)

We have measured a profile of C IV spectral line emitted from the detached diverter plasma of JT-60U with a high-wavelength resolution spectrometer, and analyzed it with PPP code. In the previous analysis, the measured spectral profile was compared with the spectral profile calculated by the PPP code with one pair of electron density and temperature. With this method, the spectral profiles measured around the X-point were well reproduced, but the spectral profile measured at a very center of the X-point was not reproduced. In the present analysis, we have succeeded to reproduce the spectral profile measured at the very center of the X-point by synthesizing two spectra calculated with two pairs of electron densities and temperatures. One pair was 1$$times$$10$$^{20}$$ m$$^{-3}$$ and 23.0 eV, and the other 1$$times$$10$$^{20}$$ m$$^{-3}$$ and 2.5 eV. The contribution to the intensity of C IV spectral line of the first pair was 65% and that of the second 35%.

Oral presentation

Numerical analysis of tungsten erosion at the plasma facing surface in DEMO reactor

Hoshino, Kazuo; Toma, Mitsunori*; Shimizu, Katsuhiro; Asakura, Nobuyuki; Tobita, Kenji; Hatayama, Akiyoshi*; Takizuka, Tomonori*

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