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Journal Articles

Determination of tungsten and molybdenum concentrations from an X-ray range spectrum in JET with the ITER-like wall configuration

Nakano, Tomohide; Shumack, A.*; Maggi, C. F.*; Reinke, M.*; Lawson, K.*; Coffey, I.*; P$"u$tterich, T.*; Brezinsek, S.*; Lipschultz, B.*; Matthews, G. F.*; et al.

Journal of Physics B; Atomic, Molecular and Optical Physics, 48(14), p.144023_1 - 144023_11, 2015/07

 Times Cited Count:27 Percentile:84.61(Optics)

The $$mbox{W}^{45+}$$ and $$mbox{W}^{46+}$$ 3p-4d inner shell excitation lines in addition to $$mbox{Mo}^{32+}$$ 2p-3s lines have been identified from the spectrum taken by an upgraded high-resolution X-ray spectrometer. It is found from analysis of the absolute intensities of the $$mbox{W}^{46+}$$ and $$mbox{Mo}^{32+}$$ lines that W and Mo concentrations are in the range of $$sim10^{-5}$$ and $$sim10^{-6}$$, respectively, with a ratio of $$sim$$ 5% for ELMy H-mode plasmas with a plasma current of 2.0- 2.5 MA, a toroidal magnetic field of 2.7 T and a neutral beam injection power of 14-18 MW. For the purpose of checking self-consistency, it is confirmed that the W concentration determined from the $$mbox{W}^{45+}$$ line is in agreement with that from the $$mbox{W}^{46+}$$ line within 20% and that the plasma effective charge determined from the continuum of the first order reflection spectrum is also in agreement with that from the second order within 50%. Further, the determined plasma effective charge is in agreement with that determined from a visible spectroscopy, confirming that the sensitivity of the X-ray spectrometer is valid and that probably the W and the Mo concentrations are also valid.

Journal Articles

Free boundary equilibrium in 3D tokamaks with toroidal rotation

Cooper, W. A.*; Brunetti, D.*; Faustin, J. M.*; Graves, J. P.*; Pfefferl$'e$, D.*; Raghunathan, M.*; Sauter, O.*; Tran, T. M.*; Chapman, I. T.*; Ham, C. J.*; et al.

Nuclear Fusion, 55(6), p.063032_1 - 063032_8, 2015/05

 Times Cited Count:1 Percentile:5.81(Physics, Fluids & Plasmas)

An approximate model for a single fluid 3D MHD equilibrium with pure isothermal toroidal flow with imposed nested magnetic flux surfaces is proposed. It recovers the rigorous toroidal rotation equilibrium description in the axisymmetric limit. The approximation is valid under conditions of nearly rigid or vanishing toroidal rotation in regions with 3D deformation of the equilibrium flux surfaces. Bifurcated helical core equilibrium simulations of long-lived modes in the MAST device demonstrate that the magnetic structure is only weakly affected by the flow but that the 3D pressure distortion is important. The pressure is displaced away from the major axis and therefore is not as noticeably helically deformed as the toroidal magnetic flux under the subsonic flow conditions. Fast particle confinement is investigated with the VENUS code. In the presence of toroidal flow, the drift orbit equations depend on the electrostatic potential associated with the rotation and quasineutrality at lowest order in Larmor radius. When the equilibrium has 3D deformations, geometrical terms appear from the evaluation of Ohm's Law that considerably complicates the description of fast particle confinement.

Journal Articles

On maximizing the ICRF antenna loading for ITER plasmas

Mayoral, M.-L.*; Bobkov, V.*; Colas, L.*; Goniche, M.*; Hosea, J.*; Kwak, J. G.*; Pinsker, R.*; Moriyama, Shinichi; Wukitch, S.*; Baity, F. W.*; et al.

Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 11 Pages, 2011/03

For any given ICRF antenna design for ITER, the maximum achievable power strongly depends on the density profiles in the SOL. It has been suggested that gas injection can be used to modify the SOL profiles and thus minimize the sensitivity of the ICRF coupling to variations in the density at the edge of the confined plasma. Recently joint experiments coordinated by the ITPA were performed to characterize further this method. An increase in SOL density during gas injection led to improved coupling for all tokamaks in this multi-machine comparison. The effectiveness of using gas injection over a wide range of conditions, as a tool to tailor the edge density in front of the ICRF antennas, is documented for different gas inlet location and plasma configurations. In addition, any deleterious effects on the confinement and interaction with the antenna near-field are not investigated.

Journal Articles

Characteristics of the H-mode pedestal in improved confinement scenarios in ASDEX Upgrade, DIII-D, JET and JT-60U

Maggi, C. F.*; Groebner, R. J.*; Oyama, Naoyuki; Sartori, R.*; Horton, L. D.*; Sips, A. C. C.*; Suttrop, W.*; ASDEX Upgrade Team; Leonard, A.*; Luce, T. C.*; et al.

Nuclear Fusion, 47(7), p.535 - 551, 2007/07

 Times Cited Count:59 Percentile:89.69(Physics, Fluids & Plasmas)

Pedestal and global plasma parameters are compared in ELMy H-modes and improved confinement discharges from ASDEX Upgrade (AUG), DIII-D, JET and JT-60U with varying net input power. The pedestal top pressure increases moderately with power, in broad agreement with the power dependence of the H98(y,2) scaling. For all machines and all scenarios a robust correlation between the total and the pedestal thermal stored energy is observed. In AUG the improved confinement is due to improved pedestal confinement in improved H-modes with early heating and to both improved pedestal and core confinement in improved H-modes with late heating. In DIII-D the increase in confinement is due to improved confinement in the plasma core. JT-60U reversed shear H-modes have strong internal transport barriers and thus improved core performance. In all four tokamaks improved edge stability is correlated with increasing total $$beta_{p}$$ and H98(y,2) increases with pedestal $$beta_{p}$$.

Journal Articles

Characteristics of the H-mode pedestal in improved confinement scenarios in ASDEX Upgrade, DIII-D, JET and JT-60U

Maggi, C. F.*; Groebner, R. J.*; Oyama, Naoyuki; Sartori, R.*; Horton, L. D.*; Sips, A. C. C.*; Suttrop, W.*; ASDEX Upgrade Team; Leonard, T.*; Luce, T. C.*; et al.

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03

Pedestal and global plasma parameters are compared in ELMy H-mode discharges from ASDEX Upgrade (AUG), DIII-D, JET and JT-60U. The increase in pedestal pressure (p$$^{PED}$$) with power is continuous, reflecting the continuous transition from "standard H-mode" to "improved confinement scenario". In AUG improved H-modes p$$^{PED}$$ increases with power due to an increase of both pedestal top density and temperature. In DIII-D p$$^{PED}$$ increases primarily due to an increase of the pedestal temperature. In JT-60U high $$beta_{pol}$$ H-modes at $$q_{95}$$ = 6.5 and high $$delta$$ the improved confinement is due to an increase of $$W_{PED}$$, while in reversed shear H-modes to an increase of $$W_{core}$$. In JET hybrid discharges at 1.4 MA $$W_{th}$$ increases with power and $$delta$$ due to an increase of $$W_{PED}$$. In all four tokamaks improved edge stability is correlated to increasing total $$beta_{pol} $$ and H98(y,2) increases with pedestal $$beta_{pol}$$.

Journal Articles

Some comments on current system of dosimetric quantities

Oda, Keiji*; Takahashi, Fumiaki; Expert Committee on Concepts of Dosimetric Quantities Used in Radiological protection, Japan Health

Proceedings of 2nd Asian and Oceanic Congress Radiological Protection (AOCRP-2) (CD-ROM), p.52 - 55, 2006/10

no abstracts in English

JAEA Reports

Proceedings of 3rd JAERI-JNC Joint Conference on Nuclear Safety Research; July 29, 2005, Tokyo

Secretariat of Third JAERI-JNC Joint Conference on Nuclear Safety Research

JAEA-Conf 2006-002, 103 Pages, 2006/03

JAEA-Conf-2006-002.pdf:8.36MB

The present report is the proceedings of third JAERI-JNC joint conference on nuclear safety research held on July 29, 2005 in Tokyo before integration of JAERI and JNC to JAEA. The conference was held for those who are relevant to nuclear industries and regulatory organizations, and general public. The nuclear safety research has been conducted in both institutes according to the Five-Year Program for Nuclear Safety Research established periodically by the Nuclear Safety Commission (NSC) and needs from the regulatory organizations. The objectives of the conference are to present its recent results and to collect views and opinions from the participants for its future program through the discussion after each presentation and panel discussion on how to conduct efficiently the nuclear safety research in the New Organization. A total of 234 people participated in the conference mainly from the nuclear industries and regulatory organizations. Through vigorous exchange of views in the panel discussion and descriptions on the questionnaires, it was obviously expressed that expectation to the safety research of the New Organization was very strong. Moreover, many valuable views were given for carrying out the nuclear safety research in the new organization and for holding a conference in future. Based on these results, it was believed that the objectives of this conference were almost achieved.

JAEA Reports

JNC Technical Review No.27

TCO*

JNC TN1340 2005-001, 131 Pages, 2005/06

JNC-TN1340-2005-001.pdf:25.15MB

None

JAEA Reports

Meeting on safety research for FBR, in FY2005

Research and Development Coordinate Section, O-arai Engineering Center

JNC TN9200 2004-002, 89 Pages, 2005/01

JNC-TN9200-2004-002.pdf:2.34MB

The 16th Meeting for Reporting Safety Research on FBR was held at the O-arai Engineering Center on the 19th of October in 2004. The 6 subjects from the 24 subjects in total have been presented in the power reactor field of fast breeder reactor, according to the selection by the sub-committees of the Sectional Meeting of Safety Research. The outcomes on these subjects in FY2003 were reported and discussed at the meeting. This meeting was open to the public. Related specialists outside of JNC were invited for the purpose of getting advice and joined the discussion. This report contains presentation papers, questions and answers, list of attendance, etc. Refer to the JNC open report*3) for detailed results of safety research in FY2003.

JAEA Reports

R&D Conference report (from first to fourth session in 2004)

Reseach and Development Coordi

JNC TN9440 2004-003, 233 Pages, 2004/10

JNC-TN9440-2004-003.pdf:11.72MB

None

JAEA Reports

Proceedings of 2nd JAERI-JNC Joint Conference on Nuclear Safety Research; February 6, 2004, Tokyo

Secretariat of Second JAERI-JNC Joint Conference on Nuclear Safety Research

JAERI-Conf 2004-013, 97 Pages, 2004/08

JAERI-Conf-2004-013.pdf:18.89MB

no abstracts in English

JAEA Reports

R&D Conference report(from fourth to ninth session in 2003)

Research and Development Coord

JNC TN9440 2004-001, 121 Pages, 2004/04

JNC-TN9440-2004-001.pdf:28.82MB

None

JAEA Reports

R&D Conference report (from first to third session in 2003)

Research and Development Coord

JNC TN9440 2003-003, 228 Pages, 2003/10

JNC-TN9440-2003-003.pdf:27.35MB

None

JAEA Reports

Proceedings of JAERI-JNC Joint Conference on Nuclear Safety Research; March 7, 2003, Tokyo

Secretariat of JAERI-JNC Joint Conference on Nuclear Safety Research

JAERI-Conf 2003-013, 110 Pages, 2003/08

JAERI-Conf-2003-013.pdf:10.97MB

no abstracts in English

JAEA Reports

None

Reseach and Development Coordi

JNC TN9440 2003-002, 105 Pages, 2003/04

JNC-TN9440-2003-002.pdf:4.71MB

None

JAEA Reports

None

Reseach and Development Coordi

JNC TN9440 2002-004, 325 Pages, 2002/01

JNC-TN9440-2002-004.pdf:11.68MB

None

JAEA Reports

Proceedings of The 3rd International Forum on Nuclear Non-Proliferation

Power Reactor and Nuclear Fuel Development Corporation

PNC TN1102 98-006, 164 Pages, 1998/02

PNC-TN1102-98-006.pdf:8.0MB

JAEA Reports

None

Power Reactor and Nuclear Fuel Development Corporation

PNC TN1410 98-002, 108 Pages, 1998/01

PNC-TN1410-98-002.pdf:11.74MB

no abstracts in English

JAEA Reports

None

Power Reactor and Nuclear Fuel Development Corporation

PNC TN1410 97-040, 162 Pages, 1997/11

PNC-TN1410-97-040.pdf:7.43MB

None

JAEA Reports

None

Power Reactor and Nuclear Fuel Development Corporation

PNC TN1700 97-005, 20 Pages, 1997/05

PNC-TN1700-97-005.pdf:4.45MB

303 (Records 1-20 displayed on this page)