P. Sichta
Princeton Plasma Physics Laboratory
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Featured researches published by P. Sichta.
Nuclear Fusion | 2015
M. Ono; J. Chrzanowski; L. Dudek; S.P. Gerhardt; P. Heitzenroeder; R. Kaita; J. Menard; E. Perry; T. Stevenson; R. Strykowsky; P. Titus; A. von Halle; M. Williams; N.D. Atnafu; W. Blanchard; M. Cropper; A. Diallo; D.A. Gates; R.A. Ellis; K. Erickson; J. C. Hosea; Ron Hatcher; S.Z. Jurczynski; S.M. Kaye; G. Labik; J. Lawson; Benoit P. Leblanc; R. Maingi; C. Neumeyer; R. Raman
The National Spherical Torus Experiment-Upgrade (NSTX-U) is the most powerful spherical torus facility at PPPL, Princeton USA. The major mission of NSTX-U is to develop the physics basis for an ST-based Fusion Nuclear Science Facility (FNSF). The ST-based FNSF has the promise of achieving the high neutron fluence needed for reactor component testing with relatively modest tritium consumption. At the same time, the unique operating regimes of NSTX-U can contribute to several important issues in the physics of burning plasmas to optimize the performance of ITER. NSTX-U further aims to determine the attractiveness of the compact ST for addressing key research needs on the path toward a fusion demonstration power plant (DEMO). The upgrade will nearly double the toroidal magnetic field BT to 1 T at a major radius of R0 = 0.93 m, plasma current Ip to 2 MA and neutral beam injection (NBI) heating power to 14 MW. The anticipated plasma performance enhancement is a quadrupling of the plasma stored energy and near doubling of the plasma confinement time, which would result in a 5–10 fold increase in the fusion performance parameter nτ T. A much more tangential 2nd NBI system, with 2–3 times higher current drive efficiency compared to the 1st NBI system, is installed to attain the 100% non-inductive operation needed for a compact FNSF design. With higher fields and heating powers, the NSTX-U plasma collisionality will be reduced by a factor of 3–6 to help explore the favourable trend in transport towards the low collisionality FNSF regime. The NSTX-U first plasma is planned for the Summer of 2015, at which time the transition to plasma operations will occur.
ieee npss symposium on fusion engineering | 1999
M. Ono; S.M. Kaye; C. Neumeyer; Yueng Kay Martin Peng; M. Williams; G. Barnes; M.G. Bell; J. Bialek; T. Bigelow; W. Blanchard; A. Brooks; Mark Dwain Carter; J. Chrzanowski; W. Davis; L. Dudek; R.A. Ellis; H.M. Fan; E. Fredd; D.A. Gates; T. Gibney; P. Goranson; Ron Hatcher; P. Heitzenroeder; J. C. Hosea; Stephen C. Jardin; Thomas R. Jarboe; D. Johnson; M. Kalish; R. Kaita; C. Kessel
The NSTX (National Spherical Torus Experiment) facility located at Princeton Plasma Physics Laboratory is the newest national fusion science experimental facility for the restructured US Fusion Energy Science Program. The NSTX project was approved in FY 97 as the first proof-of-principle national fusion facility dedicated to the spherical torus research. On Feb. 15, 1999, the first plasma was achieved 10 weeks ahead of schedule. The project was completed on budget and with an outstanding safety record. This paper gives an overview of the NSTX facility construction and the initial plasma operations.
ieee npss symposium on fusion engineering | 1997
Charles A. Gentile; M. Kalish; E. Amarescu; J. Benson; W. Blanchard; C. Bunting; S. Bush; R. Camp; A. F. Carpe; R.H. Carnevale; M. Casey; L. Ciebiera; S. Connell; M. Gibson; R. Hawryluk; Ron Hatcher; R. Hawes; S. Homer; J. C. Hosea; D. Hyatt; E. Kearns; T. Kozub; J. Langford; S.W. Langish; R. Marsala; J. Montague; A. Nagy; G. Pearson; M. Quigley; S. Raftopoulos
In April of 1993 PPPL embarked upon the tritium operations phase of the TFTR project. Four years later, in the early morning of April 4, 1997, TFTR pulsed with tritium for the last time. In those four years, approximately 1 mega Curie of tritium was processed, and a Tritium Purification System (TPS) was commissioned. During this period >1,000 invasive (line break) operations were performed with <425 Cl of tritium released to the environment. The highly successful operation of the TFTR tritium systems was due to a corporate culture which stressed the importance of safe operations and the commitment by the TFTR staff to conduct nuclear operations in an efficient and safe fashion. The operation of TFTR as a nuclear facility employed 1,096 detailed operations procedures which were adhered to by all nuclear operations personnel and included a clear chain of command for nuclear operations.
Fusion Science and Technology | 2018
V. Soukhanovskii; W. Blanchard; J. K. Dong; R. Kaita; H.W. Kugel; J. Menard; T. J. Provost; R. Raman; A.L. Roquemore; P. Sichta
Abstract A supersonic gas injector (SGI) has been developed for fueling and diagnostic applications on the National Spherical Torus Experiment (NSTX). It is comprised of a graphite converging-diverging Laval nozzle and a commercial piezoelectric gas valve mounted on a movable probe at a low-field-side midplane port location. Also mounted on the probe is a diagnostic package: a Langmuir probe, two thermocouples, and five pick-up coils for measuring toroidal, radial, vertical magnetic field components and magnetic fluctuations at the location of the SGI tip. The SGI flow rate is up to 33.25 Pa m3/ (1.75 × 1022 euterium particles/s), comparable to conventional NSTX gas injectors. The nozzle operates in a pulsed regime at room temperature and a reservoir gas pressure up to 665 kPa (5000 Torr). The deuterium jet Mach number of about 4 and the divergence half-angle of 5 to 25 deg have been measured in laboratory experiments simulating the NSTX environment. Reliable operation of the SGI and all mounted diagnostics at distances 0.01 to 0.20 m from the plasma separatrix has been demonstrated in NSTX experiments. The SGI has been used for fueling of ohmic and 2- to 4-MW neutral beam injection–heated L- and H-mode plasmas. Fueling efficiency in the range 0.1 to 0.3 has been obtained from the plasma electron inventory analysis. The SGI-fueling–based plasma discharge scenarios enabling better density control have been developed.
ieee npss symposium on fusion engineering | 2005
V. Soukhanovskii; H.W. Kugel; R. Kaita; A. L. Roquemore; M.G. Bell; W. Blanchard; C. Bush; R. Gernhardt; G. Gettelfinger; T. Gray; R. Majeski; J. Menard; T. Provost; P. Sichta; R. Raman
A supersonic gas injector (SGI) has been developed for fueling and diagnostic applications on the National Spherical Torus Experiment (NSTX). It is comprised of a graphite converging-diverging Laval nozzle and a commercial piezoelectric gas valve mounted on a movable probe at a low field side midplane port location. Also mounted on the probe is a diagnostic package: a Langmuir probe, two thermocouples and five pick-up coils for measuring toroidal, radial, vertical magnetic field components and magnetic fluctuations at the location of the SGI tip. The SGI flow rate is up to 4times1021 particles/s, comparable to conventional NSTX gas injectors. The nozzle operates in a pulsed regime at room temperature and a reservoir gas pressure up to 0.33 MPa. The deuterium jet Mach number of about 4, and the divergence half-angle of 5deg - 25deg have been measured in laboratory experiments simulating NSTX environment. In initial NSTX experiments reliable operation of the SGI and all mounted diagnostics at distances 1-20 cm from the plasma separatrix has been demonstrated. The SGI has been used for fueling of ohmic and 2-4 MW NBI heated L- and H-mode plasmas. Fueling efficiency in the range 0.1-0.3 has been obtained from the plasma electron inventory analysis