Zobrazeno 1 - 10
of 161
pro vyhledávání: '"C.B. Baxi"'
Publikováno v:
Fusion Engineering and Design. 82:731-735
During 2004 and 2005, collectors on three of the gyrotrons used at DIII-D failed due to stress cracks. In order to investigate reasons for these failures, a nonlinear elastic plastic thermal stress analysis of the collector/design was undertaken. The
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9fcfb03c1aae1874301e07088cc3a585
https://doi.org/10.1016/j.fusengdes.2007.01.016
https://doi.org/10.1016/j.fusengdes.2007.01.016
Autor:
C.B. Baxi
Publikováno v:
Fusion Engineering and Design. :633-636
The DIII–D tokamak uses three cryocondensation pumps for plasma density control. Each DIII–D pump consists of a series of concentric stainless steel tubes assembled together. The two phase (TP) helium was chosen for DIII–D because it is availab
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2f41b77b8635bc4da61b779dba0958c4
https://doi.org/10.1016/j.fusengdes.2005.06.062
https://doi.org/10.1016/j.fusengdes.2005.06.062
Publikováno v:
Fusion Engineering and Design. :323-327
The Fusion Engineering Research Experiment (FIRE) device is designed for high powerdensity and advanced physics operating modes. Due to the short distance of the divertor from theX–point, the connection lengths are short and the scrape off layer th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c70368f524be1b9bf6c8e4d182584b1c
https://doi.org/10.1016/s0920-3796(03)00197-2
https://doi.org/10.1016/s0920-3796(03)00197-2
Publikováno v:
Fusion Engineering and Design. :791-795
Since 1995, DIII-D has performed correction of magnetic field imperfections using a set of six external picture frame coils located on the vessel mid-plane. Recently, these coils have also demonstrated significant benefits when used for feedback of t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fe051866d0aba2c54d843dc73795788c
https://doi.org/10.1016/s0920-3796(03)00318-1
https://doi.org/10.1016/s0920-3796(03)00318-1
Publikováno v:
Fusion Engineering and Design. :433-437
The DIII–D program has completed a series of density control and plasma core confinement experiments this past year. These experiments were designed to investigate the performance of baffled and open divertors with single-null plasmas and particle
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4b0e9661be65fc050252b687f184efe3
https://doi.org/10.1016/s0920-3796(01)00314-3
https://doi.org/10.1016/s0920-3796(01)00314-3
Autor:
C.B. Baxi
Publikováno v:
Fusion Engineering and Design. :195-198
Divertors of several new machines, such as JT-60SU, FIRE, SST-1, ITER-RC and KSTAR, are water-cooled. This paper examines critical thermal hydraulic issues associated with the design of such divertors. The flow direction of coolant in the divertor ca
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8fcf6e9c81239538379613f71187455c
https://doi.org/10.1016/s0920-3796(01)00258-7
https://doi.org/10.1016/s0920-3796(01)00258-7
Publikováno v:
Fusion Technology. 39:923-929
General Atomics recently completed a divertor design study for JAERI for the JT-60 Super Upgrade (JT-60SU) tokamak. JT-60SU is being designed as a superconducting device for an integrated RD however, the outer and private flux baffles have an alterna
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9a3beab16ac42ce9c425de1b3238ab59
https://doi.org/10.13182/fst01-a11963358
https://doi.org/10.13182/fst01-a11963358
Autor:
Jeffrey N. Brooks, M.A. Ulrickson, T. Rognlein, D. Driemeyer, B.E. Nelson, C.B. Baxi, J. C. Wesley, C.E. Kessel, A. Hassenein
Publikováno v:
Fusion Technology. 39:378-382
A design study of a Fusion Ignition Research Experiment (FIRE) is underway to investigate and assess near term opportunities for advancing the scientific understanding of self-heated fusion plasmas. The emphasis for the FIRE program is on understandi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ade047a45e3e845abee2d630abc10684
https://doi.org/10.13182/fst01-a11963263
https://doi.org/10.13182/fst01-a11963263
Publikováno v:
Fusion Technology. 39:408-411
The Fusion Ignition Research Experiment (FIRE) is being designed as a next step in the U.S. magnetic fusion program. The FIRE tokamak has a major radius of 2 m, a minor radius of 0.525 m, and liquid nitrogen cooled copper coils. The aim is to produce
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7763aff2c32c4301fef4cfecb8ec8fec
https://doi.org/10.13182/fst01-a11963269
https://doi.org/10.13182/fst01-a11963269
Autor:
P.C. Stangeby, A.W. Leonard, R.D. Stambaugh, S. Skinner, W.P. West, N.H. Brooks, S.L. Allen, R.J. Colchin, M.E. Friend, Dennis Whyte, R.A. Moyer, J.A. Boedo, G.D. Porter, M.A. Mahdavi, M. R. Wade, A.G. Kellman, J.G. Watkins, A.W. Hyatt, M.E. Fenstermacher, R.C. Isler, R.C. O'Neill, M.J. Schaffer, R. Maingi, A.S. Bozek, C.J. Lasnier, T.C. Luce, Todd Evans, C.B. Baxi, N. S. Wolf, T.W. Petrie
Publikováno v:
Journal of Nuclear Materials. :905-909
A major upgrade of the DIII-D divertor, with the goal of enhancing impurity and density control and increasing the thermal pulse length limit of advanced tokamak (AT) plasmas has been successfully completed and commissioned. The integrated system tha
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ecaee843bdef942c476e2e7a53d6a188
https://doi.org/10.1016/s0022-3115(00)00500-6
https://doi.org/10.1016/s0022-3115(00)00500-6