Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 253

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Development of separation technique of Pu, Am, Np using solid phase extraction resin for the determination of impurity metal elements in plutonium nitrate solution by inductivity coupled plasma optical emission spectrometry

Taguchi, Shigeo; Yamamoto, Masahiko; Furuse, Takahiro*; Masaki, Yuji*; Kuno, Takehiko

JAEA-Technology 2018-005, 14 Pages, 2018/06

JAEA-Technology-2018-005.pdf:0.94MB

The method to remove Pu, Am and Np from plutonium nitrate solution recovered from spent nuclear fuel prior to ICP-OES measurement has been developed for the determination of 18 impurity metal elements (Fe, Cr, Ni, Mn, Al, Cd, V, Cu, Si, Zn, Mo, Sn, Ca, Mg, Na, Ag, Pb, B). In this method, two TRU resin packed columns were used for separation. In the first column, Pu and Am were mainly removed by adsorption. The recovered solution from the fist column was added to the second column after reduction of Np, and Am(III) and Np(IV) were removed by adsorption. The Pu nitrate solution (22g/L) of 2mL were treated by proposed method. The alpha emission nuclide was decreased to $$<$$5.8 Bq/mL in a solution diluted to 100mL. As a result of ICP-OES measurement, the recoveries of impurity metals separated by proposed method were almost 100%. This separation scheme can apply to the metal impurity elemental analysis in Pu nitrate solution recovered from spent nuclear fuel.

Journal Articles

Fast neutral particle diagnostic

Kusama, Yoshinori

Purazuma Shindan No Kiso To Oyo, p.195 - 205, 2006/03

no abstracts in English

Journal Articles

Modeling of impurity transport in high density plasma with highly enhanced radiation loss on JT-60U

Takenaga, Hidenobu; Asakura, Nobuyuki; Kubo, Hirotaka; Konoshima, Shigeru; Nakano, Tomohide; Porter, G.*; Rognlien, T.*; Rensink, M.*

Journal of Plasma and Fusion Research SERIES, Vol.7, p.35 - 39, 2006/00

no abstracts in English

Journal Articles

Shallow P donors in 3${it C}$-, 4${it H}$-, and 6${it H}$-SiC

Isoya, Junichi*; Katagiri, Masayuki*; Umeda, Takahide*; Son, N. T.*; Henry, A.*; Gali, A.*; Morishita, Norio; Oshima, Takeshi; Ito, Hisayoshi; Janz$'e$n, E.*

Materials Science Forum, 527-529, p.593 - 596, 2006/00

no abstracts in English

Journal Articles

Compatibility of advanced tokamak plasma with high density and high radiation loss operation in JT-60U

Takenaga, Hidenobu; Asakura, Nobuyuki; Kubo, Hirotaka; Higashijima, Satoru; Konoshima, Shigeru; Nakano, Tomohide; Oyama, Naoyuki; Porter, G. D.*; Rognlien, T. D.*; Rensink, M. E.*; et al.

Nuclear Fusion, 45(12), p.1618 - 1627, 2005/12

 Times Cited Count:18 Percentile:43.67(Physics, Fluids & Plasmas)

no abstracts in English

JAEA Reports

The Development of the boroncoating device for the JFT-2M

Yamamoto, Masahiro*; Okano, Fuminori; Tsuzuki, Kazuhiro; Ogawa, Hiroaki; Suzuki, Sadaaki; Shibata, Takatoshi

JAERI-Tech 2005-061, 11 Pages, 2005/09

JAERI-Tech-2005-061.pdf:0.94MB

Ferritic steel plates were installed in the JFT-2M vacuum vessel to conduct "the Advanced Material Tokamak Experiments (AMTEX)". A coating device with tri-methyl-bron(TMB)was developed to coat the ferritic steel surface with boron, since the ferritic steel is easy to rust and also has a property to absorb much impurity in the surface. The TMB gas used in the device was diluted with helium gas to 1% for ensuring workers themselves against the toxicity of the TMB. The uniformity and stability of the coated layer have been confirmed through sample tests with a microscope, whose samples had been set in the tokamak vacuum vessel. The coating thickness measured with X-ray photoelectron emission spectroscopy was roughly 130nm. In the plasma experiments after the boron coating, radiation loss in the plasma decreased to 1/3, and oxygen impurity also decreased to 1/10 compared to without the boron coating.

Journal Articles

Relation between the oxygen contents in the neutral beam and in the core plasma in JT-60U

Nakano, Tomohide; Koide, Yoshihiko; Honda, Atsushi; Umeda, Naotaka; Akino, Noboru; Higashijima, Satoru; Takenaga, Hidenobu; Kubo, Hirotaka

Purazuma, Kaku Yugo Gakkai-Shi, 81(9), p.708 - 716, 2005/09

no abstracts in English

Journal Articles

Characteristics of post-disruption runaway electrons with impurity pellet injection

Kawano, Yasunori; Nakano, Tomohide; Isayama, Akihiko; Asakura, Nobuyuki; Tamai, Hiroshi; Kubo, Hirotaka; Takenaga, Hidenobu; Bakhtiari, M.; Ide, Shunsuke; Kondoh, Takashi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 81(8), p.593 - 601, 2005/08

An experiment to investigate mitigation effects of impurity pellet injection on disruption generated runaway electrons was carried out in the JT-60U tokamak device. Deposition of impurity neon pellets into a post-disruption runaway plasma was observed with increment of bulk electron density. At the impurity pellet injection, decay time of runaway current became shorter as factor of $$sim$$2. There was an approximately linear relationship between changes in decay rate of runaway current and a photo-neutron signal which indicated loss of runaway electrons from the plasma. Consequently, enhanced loss of runaway electrons from a tokamak plasma, hence mitigation effect on them, by injection of impurity neon pellets was found.

Journal Articles

Study of plasma wall interactions in the long-pulse NB-heated discharges of JT-60U towards steady-state operation

Takenaga, Hidenobu; Asakura, Nobuyuki; Higashijima, Satoru; Nakano, Tomohide; Kubo, Hirotaka; Konoshima, Shigeru; Oyama, Naoyuki; Isayama, Akihiko; Ide, Shunsuke; Fujita, Takaaki; et al.

Journal of Nuclear Materials, 337-339, p.802 - 807, 2005/03

 Times Cited Count:14 Percentile:27.76(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Characteristics of runaway plasmas in JT-60U

Kawano, Yasunori; Nakano, Tomohide; Isayama, Akihiko; Hatae, Takaki; Konoshima, Shigeru; Oyama, Naoyuki; Kondoh, Takashi; Tamai, Hiroshi; Kubo, Hirotaka; Asakura, Nobuyuki; et al.

Europhysics Conference Abstracts (CD-ROM), 29C, 4 Pages, 2005/00

In order to mitigate the post-disruption runaway electrons, experiments has been carried out with impurity pellet injection. As a result, we have observed the prompt exhaust of the runaway electrons and the reduction of runaway plasma. We have presented one possible explanation for basic behavior of the runaway plasma current that it follows the balance of the avalanche generation of runaway electrons and their slowing down predicted by the model, including effects by synchrotron radiation. On the other hand, standing on the fact that the current quench time is extended by runaway electrons, the experiment for avoiding the current quench by runaway electrons has been carried out. The runaway electrons reinforced the discharge to survive against the low Te of less than several tens eV and an additional impurity pellet injection, and thus the plasma current was maintained and terminated as programmed. To study the dynamics of runaway electrons precisely, a new active and direct diagnostic concept using the laser inverse Compton scattering has been proposed.

Journal Articles

Compatibility of advanced tokamak plasma with high density and high radiation loss operation in JT-60U

Takenaga, Hidenobu; Asakura, Nobuyuki; Kubo, Hirotaka; Higashijima, Satoru; Konoshima, Shigeru; Nakano, Tomohide; Oyama, Naoyuki; Porter, G. D.*; Rognlien, T. D.*; Rensink, M. E.*; et al.

Proceedings of 20th IAEA Fusion Energy Conference (FEC 2004) (CD-ROM), 8 Pages, 2004/11

no abstracts in English

Journal Articles

In-out asymmetry of low-$$Z$$ impurity deposition on the JT-60 divertor tiles

Masaki, Kei; Yagyu, Junichi; Miyo, Yasuhiko; Goto, Yoshitaka*; Arai, Takashi; Hayashi, Takao; Kodama, Kozo; Sasajima, Tadayuki; Kaminaga, Atsushi; Tanabe, Tetsuo*; et al.

Journal of Nuclear Materials, 329-333(Part1), p.845 - 848, 2004/08

 Times Cited Count:0 Percentile:100(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Impurity release and deuterium retention properties of a ferritic steel wall in JFT-2M

Ogawa, Hiroaki; Yamauchi, Yuji*; Tsuzuki, Kazuhiro; Kawashima, Hisato; Sato, Masayasu; Shinohara, Koji; Kamiya, Kensaku; Kasai, Satoshi; Kusama, Yoshinori; Yamaguchi, Kaoru*; et al.

Journal of Nuclear Materials, 329-333(Part1), p.678 - 682, 2004/08

 Times Cited Count:4 Percentile:67.57(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Pulsed EPR studies of shallow donor impurities in SiC

Isoya, Junichi*; Oshima, Takeshi; Morishita, Norio; Kamiya, Tomihiro; Ito, Hisayoshi; Yamasaki, Satoshi*

Physica B; Condensed Matter, 340-342, p.903 - 907, 2003/12

 Times Cited Count:11 Percentile:45.7(Physics, Condensed Matter)

no abstracts in English

Journal Articles

Relationship between particle and heat transport in JT-60U plasmas with internal transport barrier

Takenaga, Hidenobu; Higashijima, Satoru; Oyama, Naoyuki; Bruskin, L. G.; Koide, Yoshihiko; Ide, Shunsuke; Shirai, Hiroshi; Sakamoto, Yoshiteru; Suzuki, Takahiro; Hill, K. W.*; et al.

Nuclear Fusion, 43(10), p.1235 - 1245, 2003/10

 Times Cited Count:61 Percentile:10.94(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

High performance tokamak experiments with a ferritic steel wall on JFT-2M

Tsuzuki, Kazuhiro; Kimura, Haruyuki; Kawashima, Hisato; Sato, Masayasu; Kamiya, Kensaku; Shinohara, Koji; Ogawa, Hiroaki; Hoshino, Katsumichi; Bakhtiari, M.; Kasai, Satoshi; et al.

Nuclear Fusion, 43(10), p.1288 - 1293, 2003/10

 Times Cited Count:36 Percentile:24.41(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Use of micro gas chromatography in the fuel cycle of fusion reactors

Laesser, R.*; Gruenhagen, S.*; Kawamura, Yoshinori

Fusion Engineering and Design, 69(1-4), p.813 - 817, 2003/09

 Times Cited Count:12 Percentile:36.69

Various analytical techniques exist to determine the compositions of gases handled in the fuel cycle of future fusion machines. Gas chromatography was found to be the most appropriate method. The main disadvantages of conventional gas chromatography were the long retention times for the heavy hydrogen species of more than half an hour. Recent progress in the development of micro-gas chromatography has reduced these retention times to approximately 3 minutes. The usefulness of micro-gas chromatography for the analysis of hydrogen and impurity gas mixtures in the fuel cycle of future fusion machines is presented and the advantages and draw backs are discussed.

Journal Articles

Grain boundary embrittlement of light water reactor pressure vessel steels

Nishiyama, Yutaka; Suzuki, Masahide

Kinzoku, 73(8), p.48 - 52, 2003/08

no abstracts in English

Journal Articles

Particle transport analyses

Takenaga, Hidenobu

Purazuma, Kaku Yugo Gakkai-Shi, 79(8), p.790 - 804, 2003/08

no abstracts in English

Journal Articles

Feasibility of local fast ion distribution function measurement on JT-60U by means of neutral heating beams

Mironov, M. I.*; Khudoleev, A. V.*; Kusama, Yoshinori

Proceedings of 30th EPS Conference on Controlled Fusion and Plasma Physics (CD-ROM), 4 Pages, 2003/07

no abstracts in English

253 (Records 1-20 displayed on this page)