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Journal Articles

Ground-state configuration of neutron-rich $$^{35}$$Al via Coulomb breakup

Chakraborty, S.*; Datta, U.*; Aumann, T.*; Beceiro-Novo, S.*; Boretzky, K.*; Caesar, C.*; Carlson, B. V.*; Catford, W. N.*; Chartier, M.*; Cortina-Gil, D.*; et al.

Physical Review C, 96(3), p.034301_1 - 034301_9, 2017/09

 Times Cited Count:2 Percentile:27.8(Physics, Nuclear)

no abstracts in English

Journal Articles

$$beta$$-delayed fission of $$^{186,188}$$Bi isotopes

Lane, J. F. W.*; Andreyev, A. N.*; Antalic, S.*; Ackermann, D.*; Gerl, J.*; He${ss}$berger, F. P.*; Hofmann, S.*; Huyse, M.*; Kettunen, H.*; Kleinb$"o$hl, A.*; et al.

Physical Review C, 87(1), p.014318_1 - 014318_7, 2013/01

 Times Cited Count:15 Percentile:68.41(Physics, Nuclear)

Journal Articles

ITER test blanket module error field simulation experiments at DIII-D

Schaffer, M. J.*; Snipes, J. A.*; Gohil, P.*; de Vries, P.*; Evans, T. E.*; Fenstermacher, M. E.*; Gao, X.*; Garofalo, A. M.*; Gates, D. A.*; Greenfield, C. M.*; et al.

Nuclear Fusion, 51(10), p.103028_1 - 103028_11, 2011/10

 Times Cited Count:33 Percentile:80.68(Physics, Fluids & Plasmas)

Experiments at DIII-D investigated the effects of ferromagnetic error fields similar to those expected from proposed ITER Test Blanket Modules (TBMs). Studied were effects on: plasma rotation and locking; confinement; L-H transition; edge localized mode (ELM) suppression by resonant magnetic perturbations; ELMs and the H-mode pedestal; energetic particle losses; and more. The experiments used a 3-coil mock-up of 2 magnetized ITER TBMs in one ITER equatorial port. The experiments did not reveal any effect likely to preclude ITER operations with a TBM-like error field. The largest effect was slowed plasma toroidal rotation v across the entire radial profile by as much as $$Delta v/v_{0} sim 50%$$ via non-resonant braking. Changes to global $$Delta n/n_{0}$$, $$Delta v/v_{0}$$ and $$Delta H_{98}/H_{98,0}$$ were $$sim$$3 times smaller. These effects are stronger at higher $$beta$$ and lower $$v_{0}$$. Other effects were smaller.

Journal Articles

Magnetic excitations in infinite-layer antiferromagnetic insulator

Tomiyasu, Keisuke*; Kageyama, Hiroshi*; Lee, C.*; Whangbo, M. H.*; Tsujimoto, Yoshihiro*; Yoshimura, Kazuyoshi*; Taylor, J. W.*; Llobet, A.*; Trouw, F.*; Kakurai, Kazuhisa; et al.

Journal of the Physical Society of Japan, 79(3), p.034707_1 - 034707_4, 2010/03

 Times Cited Count:16 Percentile:66.37(Physics, Multidisciplinary)

Journal Articles

Off-axis neutral beam current drive for advanced scenario development in DIII-D

Murakami, Masanori*; Park, J. M.*; Petty, C. C.*; Luce, T. C.*; Heidbrink, W. W.*; Osborne, T. H.*; Prater, R.*; Wade, M. R.*; Anderson, P. M.*; Austin, M. E.*; et al.

Nuclear Fusion, 49(6), p.065031_1 - 065031_8, 2009/06

 Times Cited Count:43 Percentile:82.92(Physics, Fluids & Plasmas)

Modification of the two existing DIII-D neutral beam lines is planned to allow vertical steering to provide off-axis neutral beam current drive (NBCD) peaked as far off-axis as half the plasma minor radius. New calculations for a downward-steered beam indicate strong current drive with good localization off-axis so long as the toroidal magnetic field, BT, and the plasma current, Ip, point in the same direction. This is due to good alignment of neutral beam injection (NBI) with the local pitch of the magnetic field lines. This model has been tested experimentally on DIII-D by an injecting equatorially-mounted NBs into reduced size plasmas that are vertically displaced with respect to the vessel midplane. The existence of off-axis NBCD is evident in the changes seen in sawtooth behavior in the internal inductance. By shifting the plasma upward or downward, or by changing the sign of the toroidal field, measured off-axis NBCD profiles measured with motional Stark effect data and internal loop voltage show a difference in amplitude (40%-45%) consistent with predicted differences predicted by the changed NBI alignment with respect to the helicity of the magnetic field lines. The effects of NB injection direction relative to field line helicity can be large even in ITER: off-axis NBCD can be increased by more than 20% if the BT direction is reversed. Modification of the DIII-D NB system will strongly support scenario development for ITER and future tokamaks as well as providing flexible scientific tools for understanding transport, energetic particles and heating and current drive.

Journal Articles

Low energy vibrational excitations characteristic of superionic glass

Nakamura, Mitsutaka; Iwase, Hiroki; Arai, Masatoshi; Kartini, E.*; Russina, M.*; Yokoo, Tetsuya*; Taylor, J. W.*

Physica B; Condensed Matter, 385-386(1), p.552 - 554, 2006/11

 Times Cited Count:3 Percentile:18.02(Physics, Condensed Matter)

The mechanism of high ionic conductivity in superionic glass constitute an unsolved problem in the field of science.Here we performed inelastic neutron scattering measurements of superionic glass system (AgI)$$_{x}$$(Ag$$_{2}$$S)$$_{x}$$(AgPO$$_{3}$$)$$_{1-2x}$$ by using MARI spectrometer at ISIS, and found that the $$Q$$-dependence of inelastic intensity in the energy region from 1 to 3 meV of superionic phase glass shows an excess intensity above $$Q$$=1.8$AA$^{-1}$$ compared with insulator phase one. Similar phenomena were also observed in another superionic glass (AgI)$$_{0.5}$$(AgPO$$_{3}$$)$$_{0.5}$$ by using NEAT spectrometer at HMI with high resolution measurement. These results clearly suggest peculiar low energy vibrational excitations should be universal features of superionic glass.

Journal Articles

Unique vibrational excitations in superionic conducting glass

Nakamura, Mitsutaka; Arai, Masatoshi; Kartini, E.*; Taylor, J. W.*; Russina, M.*

AIP Conference Proceedings 832, p.504 - 507, 2006/05

Superionic glasses (AgI)$$_{0.33}$$(Ag$$_{2}$$S)$$_{0.33}$$(AgPO$$_{3}$$)$$_{0.34}$$ and (AgI)$$_{0.5}$$(AgPO$$_{3}$$)$$_{0.5}$$ have high ionic conductivity at room temperature ($$sigmasim10^{-2}$$S/cm). The inelastic neutron scattering measurements show that the superionic glass has larger intensity in low-energy region compared with undoped insulator glass (AgPO$$_{3}$$). For superionic glasses we find an excess intensity above $$Q$$=1.8$AA$^{-1}$$ and peak profile at around 2.2$AA$^{-1}$$ by investigating the $$Q$$-dependent features in low-energy region. These phenomena should be universal features of silver-salt superionic glass. We suppose that Ag-Ag dynamical correlation should promote the successive hopping process, and result in high ionic conductivity.

Journal Articles

Characterization of disruption phenomenology in ITER

Yoshino, Ryuji; D.J.Campbell*; E.Fredrickson*; Fujisawa, Noboru; N.Granetz*; Gruber, O.*; T.C.Hender*; D.A.Humphreys*; N.Ivanov*; S.Jardin*; et al.

Fusion Energy 2000 (CD-ROM), 4 Pages, 2001/05

no abstracts in English

Journal Articles

Lessons learned from the ITER safety approach for future fusion facilities

Gordon, C.*; Bartels, H.-W.*; Honda, Takuro; Iseli, M.*; Raeder, J.*; Topilski, L.*; Moshonas, K.*; Taylor, N.*

Fusion Engineering and Design, 54(3-4), p.397 - 403, 2001/04

 Times Cited Count:2 Percentile:19.67(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

TSTA/FCU-JFCU tritium experiment on breeding blanket interface under the collaboration of JAERI-US/DOE (extended Annex IV); March 1993

Enoeda, Mikio; Yamanishi, Toshihiko; Yamada, Masayuki; Konishi, Satoshi; Okuno, Kenji; Willms, R. S.*; Taylor, D.*; W.Harbin*; Bartlit, J. R.*; Anderson, J. L.*

JAERI-Research 95-034, 29 Pages, 1995/05

JAERI-Research-95-034.pdf:0.99MB

no abstracts in English

Journal Articles

Operation of a simulated non-steady tokamak fuel loop using the tritium systems test assembly

Konishi, Satoshi; Yamanishi, Toshihiko; Enoeda, Mikio; Hayashi, Takumi; Ohira, Shigeru; Yamada, Masayuki; Suzuki, Takumi; Okuno, Kenji; Sherman, R. H.*; Willms, R. S.*; et al.

Fusion Engineering and Design, 28, p.258 - 264, 1995/00

 Times Cited Count:4 Percentile:43.46(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Separation characteristics of cryogenic distillation column having feedback stream; Separation experiment with H-D system

Yamanishi, Toshihiko; Hayashi, Takumi; Nakamura, Hirofumi; Okuno, Kenji; Sherman, R. H.*; Taylor, D.*; Barnes, J. W.*; Bartlit, J. R.*

JAERI-M 93-188, 31 Pages, 1993/10

JAERI-M-93-188.pdf:0.8MB

no abstracts in English

JAEA Reports

Joint operation of the TSTA under the collaboration between JAERI and U.S.-DOE; TSTA extended loop operation with 100 grams of tritium on April-May, 1992

Hayashi, Takumi; Nakamura, Hirofumi; Konishi, Satoshi; Inoue, Masahiko*; Hirata, Kazuhiro*; Okuno, Kenji; Naruse, Yuji; Anderson, J. L.*; Sherman, R. H.*; Willms, R. S.*; et al.

JAERI-M 93-083, 54 Pages, 1993/03

JAERI-M-93-083.pdf:1.64MB

no abstracts in English

JAEA Reports

Joint operation of the TSTA with the J-FCU under the collaboration between JAERI and U.S.-DOE; A First integrated tritium test between J-FCU and ISS on October, 1991

Hayashi, Takumi; Nakamura, Hirofumi; Konishi, Satoshi; Yamanishi, Toshihiko; Inoue, Masahiko*; Hirata, Kazuhiro*; Okuno, Kenji; Naruse, Yuji; Anderson, J. L.*; Barnes, J. W.*; et al.

JAERI-M 93-081, 35 Pages, 1993/03

JAERI-M-93-081.pdf:1.19MB

no abstracts in English

Journal Articles

Application of sidestream recycle to the separation of hydrogen isotopes by cryogenic distillation

Sherman, R. H.*; Taylor, D. J.*; Barnes, J. W.*; Yamanishi, Toshihiko; Enoeda, Mikio; Konishi, Satoshi; Okuno, Kenji

Proceedings of 15th IEEE/NPSS Symposium on Fusion Engineering, p.77 - 79, 1993/00

no abstracts in English

Oral presentation

Results of ITER test blanket module mock-up experiments on DIII-D

Snipes, J. A.*; Schaffer, M. J.*; Gohil, P.*; de Vries, P.*; Fenstermacher, M. E.*; Evans, T. E.*; Gao, X. M.*; Garofalo, A.*; Gates, D. A.*; Greenfield, C. M.*; et al.

no journal, , 

A series of experiments was performed on DIII-D to mock-up the field that will be induced in a pair of ferromagnetic Test Blanket Modules (TBMs) in ITER to determine the effects of such error fields on plasma operation and performance. A set of coils producing both poloidal and toroidal fields was placed inside a re-entrant horizontal port close to the plasma. The coils produce a localized ripple due to the toroidal field (TF) + TBM up to 5.7%, which is more than four times that expected from a pair of representative 1.3 ton TBMs in ITER. The experiments show that the reduction in the toroidal rotation is sensitive to the ripple. On the other hand, the confinement is reduced by up to 15-18% for local ripple $$ge$$ 3% but is hardly affected at 1.7% local ripple.

Oral presentation

Powder inelastic neutron scattering study of infinite-layer ferrite SrFeO$$_{2}$$

Tomiyasu, Keisuke*; Kageyama, Hiroshi*; Tsujimoto, Yoshihiro*; Yoshimura, Kazuyoshi*; Taylor, J. W.*; Llobet, A.*; Kakurai, Kazuhisa; Yamada, Kazuyoshi*

no journal, , 

no abstracts in English

17 (Records 1-17 displayed on this page)
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