WorldCat Identities

姬路工業大学

Overview
Works: 20 works in 23 publications in 2 languages and 28 library holdings
Genres: Periodicals 
Publication Timeline
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Most widely held works by 姬路工業大学
Himeji Kōgyō Daigaku kenkyū hōkoku = Reports of the Himeji Kogyo Daigaku( )

in Japanese and held by 4 WorldCat member libraries worldwide

Issue for 1951 has articles in both sciences and humanities
Himeji Kōgyō Daigaku kenkyū hōkoku. Reports of Himeji Institute of Technology( )

in Japanese and held by 3 WorldCat member libraries worldwide

Himeji kōgyō daigaku gojūnenshi( Book )

2 editions published in 1995 in Japanese and held by 2 WorldCat member libraries worldwide

LASTI annual report( )

in English and held by 2 WorldCat member libraries worldwide

Himeji Kōgyō Daigaku kenkyū hōkoku by Himeji Kōgyō Daigaku( )

in English and Japanese and held by 2 WorldCat member libraries worldwide

Himeji kōgyō daigaku kenkyū hōkoku. A = Reports of Himeji Institute of Technology( )

in Japanese and held by 2 WorldCat member libraries worldwide

Himeji kōgyō daigaku kenkyū hōkoku = Reports of the Himeji Kogyo Daigaku( )

in Japanese and held by 1 WorldCat member library worldwide

Recent progress on the National Spherical Torus Experiment by D. A Gates( Book )

1 edition published in 2002 in English and held by 1 WorldCat member library worldwide

Himeji kōgyō daigaku kenkyū hōkoku. ippan kyōiku kankei( )

in Japanese and held by 1 WorldCat member library worldwide

Results of NSTX heating experiments by D Mueller( Book )

1 edition published in 2002 in English and held by 1 WorldCat member library worldwide

The National Spherical Torus Experiment (NSTX) at Princeton is designed to assess the potential of the low-aspect-ratio spherical torus concept for magnetic plasma confinement. The plasma has been heated by up to 5 MW of neutral beam injection, NBI, at an injection energy of 90 keV and up to 6 MW of high harmonic fast wave, HHFW, at 30 MHz. NSTX has achieved beta T of 32%. A variety of MHD phenomena have been observed to limit eta. NSTX has now begun addressing E scaling, eta limits and current drive issues. During the NBI heating experiments, a broad Ti profile with Ti up to 2 keV, Ti> Te and a large toroidal rotation. Transport analysis suggests that the impurity ions have diffusivities approaching neoclassical. For L-Mode plasmas, E is up to two times the ITER-89P L-Mode scaling and exceeds the ITER-98pby2 H-Mode scaling in some cases. Transitions to H-Mode have been observed which result in an approximate doubling of tE. after the transition in some conditions. During HH FW heating, Te> Ti and Te up to 3.5 keV were observed. Current drive has been studied using coaxial helicity injection (CHI), which has produced 390 kA of toroidal current and HHFW, which has produced H-modes with significant bootstrap current fraction at low Ip, high q and high{sub etap}
Himeji kōgyō daigaku sanjūnenshi( Book )

1 edition published in 1973 in Japanese and held by 1 WorldCat member library worldwide

The National Spherical Torus Experiment (NSTX) Research Program and Progress Towards High Beta, Long PulseOperating Scenarios by E. J Synakowski( Book )

1 edition published in 2002 in English and held by 1 WorldCat member library worldwide

A major research goal of the National Spherical Torus Experiment is establishing long-pulse, high-beta, high-confinement operation and its physics basis. This research has been enabled by facility capabilities developed over the last two years, including neutral-beam (up to 7 MW) and high-harmonic fast-wave heating (up to 6 MW), toroidal fields up to 6 kG, plasma currents up to 1.5 MA, flexible shape control, and wall preparation techniques. These capabilities have enabled the generation of plasmas with <beta {sub T}> up to 35%. Normalized beta values often exceed the no wall limit, and studies suggest that passive wall mode stabilization is enabling this for broad pressure profiles characteristic of H-mode plasmas. The viability of long, high bootstrap-current fraction operations has been established for ELMing H-mode plasmas with toroidal beta values in excess of 15% and sustained for several current relaxation times. Improvements in wall conditioning and fueling are likely contributing to a reduction in H-mode power thresholds. Electron thermal conduction is the dominant thermal loss channel in auxiliary-heated plasmas examined thus far. High-harmonic fast-wave (HHFW) effectively heats electrons, and its acceleration of fast beam ions has been observed. Evidence for HHFW current drive is by comparing of the loop voltage evolution in plasmas with matched density and temperature profiles but varying phases of launched HHFW waves. A peak heat flux of 10 MW/m superscript ''2'' has been measured in the H-mode, with large asymmetries in the power deposition being observed between the inner and outer strike points. Noninductive plasma start-up studies have focused on coaxial helicity injection. With this technique, toroidal currents up to 400 kA have been driven, and studies to assess flux closure and coupling to other current-drive techniques have begun
Ron'en( )

in Japanese and held by 1 WorldCat member library worldwide

HIF2001 : 5th Harima International Forum, Harima Science Garden City, Japan by Harima International Forum( Book )

1 edition published in 2002 in English and held by 1 WorldCat member library worldwide

Hit spring news( )

in Japanese and held by 1 WorldCat member library worldwide

 
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Alternative Names
Himeji Institute of Technology

Himeji Kogyo Daigaku

Himeji Technical College

Hyogo Kenritsu Daigaku - Himeji Shinzaike Campus

Hyogo Kenritsu University - Himeji Shinzaike Campus

Institute of Technology

Institute of Technology Himeji

Kōgyō-Daigaku

Kōgyō-Daigaku Himeji

University of Hyogo - Himeji Human Science and Environment Campus

ヒメジ コウギョウ ダイガク

兵庫県立姫路工業大学

姬路工業大学

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