Network


Latest external collaboration on country level. Dive into details by clicking on the dots.

Hotspot


Dive into the research topics where S. P. Oliva is active.

Publication


Featured researches published by S. P. Oliva.


Nuclear Fusion | 2003

Tokamak-like confinement at a high beta and low toroidal field in the MST reversed field pinch

J.S. Sarff; A. F. Almagri; J. K. Anderson; T. M. Biewer; Arthur Blair; M. Cengher; Brett Edward Chapman; P. K. Chattopadhyay; D. Craig; D.J. Den Hartog; F. Ebrahimi; G. Fiksel; Cary Forest; J.A. Goetz; D. J. Holly; B. Hudson; Thomas W. Lovell; K.J. McCollam; Paul Nonn; R. O'Connell; S. P. Oliva; Stewart C. Prager; James Christian Reardon; Mike Thomas; M. D. Wyman; D. L. Brower; W. X. Ding; S. D. Terry; Mark Dwain Carter; V. I. Davydenko

Energy confinement comparable with tokamak quality is achieved in the Madison Symmetric Torus (MST) reversed field pinch (RFP) at a high beta and low toroidal magnetic field. Magnetic fluctuations normally present in the RFP are reduced via parallel current drive in the outer region of the plasma. In response, the electron temperature nearly triples and beta doubles. The confinement time increases ten-fold (to ~10 ms), which is comparable with L- and H-mode scaling values for a tokamak with the same plasma current, density, heating power, size and shape. Runaway electron confinement is evidenced by a 100-fold increase in hard x-ray bremsstrahlung. Fokker–Planck modelling of the x-ray energy spectrum reveals that the high energy electron diffusion is independent of the parallel velocity, uncharacteristic of magnetic transport and more like that for electrostatic turbulence. The high core electron temperature correlates strongly with a broadband reduction of resonant modes at mid-radius where the stochasticity is normally most intense. To extend profile control and add auxiliary heating, rf current drive and neutral beam heating are in development. Low power lower-hybrid and electron Bernstein wave injection experiments are underway. Dc current sustainment via ac helicity injection (sinusoidal inductive loop voltages) is also being tested. Low power neutral beam injection shows that fast ions are well-confined, even in the presence of relatively large magnetic fluctuations.


Nuclear Fusion | 2009

Improved-confinement plasmas at high temperature and high beta in the MST RFP

B.E. Chapman; Joon-Wook Ahn; A. F. Almagri; J. K. Anderson; F. Bonomo; D. L. Brower; D. R. Burke; K.J. Caspary; D.J. Clayton; S.K. Combs; W.A. Cox; D. Craig; B.H. Deng; D.J. Den Hartog; W. X. Ding; F. Ebrahimi; D.A. Ennis; G. Fiksel; Cary Forest; C.R. Foust; P. Franz; S. Gangadhara; J.A. Goetz; M. C. Kaufman; J.G. Kulpin; A. V. Kuritsyn; Richard Magee; M. C. Miller; V.V. Mirnov; Paul Nonn

We have increased substantially the electron and ion temperatures, the electron density, and the total beta in plasmas with improved energy confinement in the Madison Symmetric Torus (MST). The improved confinement is achieved with a well-established current profile control technique for reduction of magnetic tearing and reconnection. A sustained ion temperature >1?keV is achieved with intensified reconnection-based ion heating followed immediately by current profile control. In the same plasmas, the electron temperature reaches 2?keV, and the electron thermal diffusivity drops to about 2?m2?s?1. The global energy confinement time is 12?ms. This and the reported temperatures are the largest values yet achieved in the reversed-field pinch (RFP). These results were attained at a density ~1019?m?3. By combining pellet injection with current profile control, the density has been quadrupled, and total beta has nearly doubled to a record value of about 26%. The Mercier criterion is exceeded in the plasma core, and both pressure-driven interchange and pressure-driven tearing modes are calculated to be linearly unstable, yet energy confinement is still improved. Transient momentum injection with biased probes reveals that global momentum transport is reduced with current profile control. Magnetic reconnection events drive rapid momentum transport related to large Maxwell and Reynolds stresses. Ion heating during reconnection events occurs globally, locally, or not at all, depending on which tearing modes are involved in the reconnection. To potentially augment inductive current profile control, we are conducting initial tests of current drive with lower-hybrid and electron-Bernstein waves.


Nuclear Fusion | 1995

Biased H mode experiments in Phaedrus-T

E.Y. Wang; Xin Wang; D. Diebold; M. Doczy; D. Edgell; Noah Hershkowitz; T. Intrator; G. Rant; S. P. Oliva; S. Regan; J. Sorensen; M. Vukovic; G. Winz; S. Wurkitch; R. Breun; D. Brouchous; M. Cekic; B. Cui; M. Kishinevsky; J.A. Meyer; P.H. Probert

Inserting a positively biased electrode to just inside the Phaedrus-T tokamak limiter results in typical H mode behaviour (i.e. Hα or Dα drop, density rise, increase in stored energy, profile steepening, and reduction of edge turbulence and radial transport) in deuterium, hydrogen and helium discharges. Hα or Dα emission suggests that the improvement in particle confinement with H mode is poloidally asymmetric, with the greatest improvement occurring on the low field side. The radial conductivity is examined and measured values are compared with theory


Physics of Plasmas | 2005

Dynamo-free plasma in the reversed-field pinch : Advances in understanding the reversed-field pinch improved confinement mode

J. K. Anderson; J. R. Adney; A. F. Almagri; Arthur Blair; D. L. Brower; M. Cengher; B.E. Chapman; S. Choi; D. Craig; Diane Renee Demers; D.J. Den Hartog; B.H. Deng; W. X. Ding; F. Ebrahimi; D.A. Ennis; G. Fiksel; Cary Forest; P. Franz; J.A. Goetz; Richard William Harvey; D. J. Holly; B. Hudson; M. C. Kaufman; Thomas W. Lovell; L. Marrelli; P. Martin; K.J. McCollam; V.V. Mirnov; Paul Nonn; R. O’Connell

Generation and sustainment of the reversed field pinch (RFP) magnetic configuration normally relies on dynamo activity. The externally applied electric field tends to drive the equilibrium away from the relaxed, minimum energy state which is roughly described by a flat normalized parallel current density profile and is at marginal stability to tearing modes. Correlated fluctuations of magnetic field and velocity create a dynamo electric field which broadens the parallel current density profile, supplying the necessary edge current drive. These pervasive magnetic fluctuations are also responsible for destruction of flux surfaces, relegating the standard RFP to a stochastic-magnetic transport-limited device. Application of a tailored electric field profile (which matches the relaxed current density profile) allows sustainment of the RFP configuration without dynamo-driven edge current. The method used to ascertain that a dynamo-free RFP plasma has been created is reported here in detail. Several confinement...


Nuclear Fusion | 2005

Overview of results in the MST reversed field pinch experiment

Stewart C. Prager; J. R. Adney; A. F. Almagri; J. K. Anderson; Arthur Blair; D. L. Brower; M. Cengher; B.E. Chapman; S. Choi; D. Craig; S.K. Combs; Diane Renee Demers; D.J. Den Hartog; B.H. Deng; W. X. Ding; F. Ebrahimi; D.A. Ennis; G. Fiksel; Richard Fitzpatrick; C.R. Foust; Cary Forest; P. Franz; L. Frassinetti; J.A. Goetz; D. J. Holly; B. Hudson; M. C. Kaufman; Thomas W. Lovell; L. Marrelli; P. Martin

Confinement in the reversed field pinch (RFP) has been shown to increase strongly with current profile control. The MST RFP can operate in two regimes: the standard regime with a naturally occurring current density profile, robust reconnection and dynamo activity; and the improved confinement regime with strong reduction in reconnection, dynamo and transport. New results in standard plasmas include the observation of a strong two-fluid Hall effect in reconnection and dynamo, the determination that the m = 0 edge resonant mode is nonlinearly driven, and the determination that tearing modes can lock to the wall via eddy currents in the shell. New results in improved confinement plasmas include observations that such plasmas are essentially dynamo-free, contain several isolated magnetic islands (as opposed to a stochastic field) and contain reduced high frequency turbulence. Auxiliary current drive and heating is now critical to RFP research. In MST, a programme to apply auxiliary systems to the RFP is underway and progress has accrued in several techniques, including lower hybrid and electron Bernstein wave injection, ac helicity injection current drive, pellet injection and neutral beam injection.


Nuclear Fusion | 2009

Plasma behaviour at high β and high density in the Madison Symmetric Torus RFP

M. D. Wyman; B.E. Chapman; Joon-Wook Ahn; A. F. Almagri; J. K. Anderson; F. Bonomo; D. L. Brower; S.K. Combs; D. Craig; D.J. Den Hartog; B.H. Deng; W. X. Ding; F. Ebrahimi; D.A. Ennis; G. Fiksel; C.R. Foust; P. Franz; S. Gangadhara; J.A. Goetz; R. O'Connell; S. P. Oliva; Stewart C. Prager; J.A. Reusch; J.S. Sarff; H.D. Stephens; T. Yates

Pellet fuelling of improved confinement Madison Symmetric Torus (MST) plasmas has resulted in high density and high plasma beta. The density in improved confinement discharges has been increased fourfold, and a record plasma beta (βtot = 26%) for the improved confinement reversed-field pinch (RFP) has been achieved. At higher β, a new regime for instabilities is accessed in which local interchange and global tearing instabilities are calculated to be linearly unstable, but experimentally, no severe effect, e.g., a disruption, is observed. The tearing instability, normally driven by the current gradient, is driven by the pressure gradient in this case, and there are indications of increased energy transport (as compared with low-density improved confinement). Pellet fuelling is also compared with enhanced edge fuelling of standard confinement RFP discharges for the purpose of searching for a density limit in MST. In standard-confinement discharges, pellet fuelling peaks the density profile where edge fuelling cannot, but transport appears unchanged. For a limited range of plasma current, MST discharges with edge fuelling are constrained to a maximum density corresponding to the Greenwald limit. This limit is surpassed in pellet-fuelled improved confinement discharges.


Physics of Plasmas | 2008

High-β, improved confinement reversed-field pinch plasmas at high density

M. D. Wyman; B.E. Chapman; Joon-Wook Ahn; A. F. Almagri; J. K. Anderson; F. Bonomo; D. L. Brower; S.K. Combs; D. Craig; D.J. Den Hartog; B.H. Deng; W. X. Ding; F. Ebrahimi; D.A. Ennis; G. Fiksel; C.R. Foust; P. Franz; S. Gangadhara; J.A. Goetz; R. O'Connell; S. P. Oliva; Stewart C. Prager; J.A. Reusch; J.S. Sarff; H.D. Stephens; T. Yates

In Madison Symmetric Torus [Dexter et al., Fusion Technol. 19, 131 (1991)] discharges where improved confinement is brought about by modification of the current profile, pellet injection has quadrupled the density, reaching ne=4×1019m−3. Without pellet injection, the achievable density in improved confinement discharges had been limited by edge-resonant tearing instability. With pellet injection, the total beta has been increased to 26%, and the energy confinement time is comparable to that at low density. Pressure-driven local interchange and global tearing are predicted to be linearly unstable. Interchange has not yet been observed experimentally, but there is possible evidence of pressure-driven tearing, an instability usually driven by the current gradient in the reversed-field pinch.


Nuclear Fusion | 2007

Recent improvements in confinement and beta in the MST reversed-field pinch

D.J. Den Hartog; J. W. Ahn; A. F. Almagri; J. K. Anderson; A. D. Beklemishev; Arthur Blair; M. T. Borchardt; D. L. Brower; D. R. Burke; M. Cengher; B.E. Chapman; S. Choi; D.J. Clayton; W.A. Cox; S.K. Combs; D. Craig; H. D. Cummings; V. I. Davydenko; Diane Renee Demers; B.H. Deng; W. X. Ding; F. Ebrahimi; D.A. Ennis; G. Fiksel; C.R. Foust; Cary Forest; P. Franz; L. Frassinetti; S. Gangadhara; J.A. Goetz

In the general area of confinement improvement and concept advancement, recent results in the Madison Symmetric Torus (MST) reversed-field pinch (RFP) include good confinement of both thermal and large-orbit ions and near doubling of total beta to 26% with deuterium pellet injection. Current profile control enables MST to reduce stochastic transport and achieve tokamak-like confinement. In standard RFP operation, substantial MHD tearing mode activity results in stochastic transport and an energy confinement time of about 1 ms in MST. Application of inductive current profile control reduces MHD activity and accompanying stochasticity, improving confinement by about a factor of ten. Previous work concentrated on electron confinement in improved-confinement RFP operation. Recent work confirms that ions are also well confined, and that high beta and improved confinement can be achieved simultaneously. PACS numbers: 52.55.Hc, 52.55.Dy (Some figures in this article are in colour only in the electronic version)


RADIO FREQUENCY POWER IN PLASMAS: 17th Topical Conference on Radio Frequency Power in Plasmas | 2007

Validating the Lower Hybrid Interdigital-line Antenna on MST

Michael Kaufman; J.A. Goetz; D. R. Burke; A. F. Almagri; S. P. Oliva; J.G. Kulpin

Lower hybrid current drive has been posited as a means to reduce tearing fluctuations and improve confinement in the reversed field pinch. The third generation interdigital‐line antenna has been installed in MST and preliminary testing has been completed. Source power to the antenna has been increased to >220 kW in both feed directions. Under vacuum conditions the n∥ spectrum is peaked at ∼7.5 as expected with excellent directionality. External tuning gives a VSWR <1.3 under most operating conditions; however, power diagnostics on the resonators show a standing wave on the antenna which could affect launch spectrum. Initial plasma parameter surveys show behavior similar to the previous generation antenna. Hard x‐ray detectors show flux is toroidally peaked, but still indicative of rf‐plasma interaction.


RADIO FREQUENCY POWER IN PLASMAS: 16th Topical Conference on Radio Frequency Power in Plasmas | 2005

Lower Hybrid Antenna Design for MST

J.A. Goetz; Mike Thomas; Michael Kaufman; S. P. Oliva

Inter‐digital line antennas are being used to test the feasibility of lower hybrid current drive in MST. The antennas use λ/4 resonators and launch slow waves at 800 MHz with n∥ ∼ 7.5. Routine operation has been achieved with a good impedance match between antenna and plasma. High power antenna design improvements include larger vacuum feed‐throughs, better impedance matching, and rf instrumentation on all resonators. The antenna and feed‐through modeling was performed with CST Microwave Studio™. The pulse‐forming network that powers the klystron is being upgraded to a 50 kV – 30 ms pulse. The goal for the LHCD system on MST is a modular design that can handle 300 kW per antenna.

Collaboration


Dive into the S. P. Oliva's collaboration.

Top Co-Authors

Avatar

J.S. Sarff

University of Wisconsin-Madison

View shared research outputs
Top Co-Authors

Avatar

A. F. Almagri

University of Wisconsin-Madison

View shared research outputs
Top Co-Authors

Avatar

D. Craig

University of Wisconsin-Madison

View shared research outputs
Top Co-Authors

Avatar

D. L. Brower

University of California

View shared research outputs
Top Co-Authors

Avatar

D.J. Den Hartog

University of Wisconsin-Madison

View shared research outputs
Top Co-Authors

Avatar

J.A. Goetz

University of Wisconsin-Madison

View shared research outputs
Top Co-Authors

Avatar

G. Fiksel

University of Wisconsin-Madison

View shared research outputs
Top Co-Authors

Avatar

Stewart C. Prager

University of Wisconsin-Madison

View shared research outputs
Top Co-Authors

Avatar

B.E. Chapman

University of Wisconsin-Madison

View shared research outputs
Top Co-Authors

Avatar

S.K. Combs

Oak Ridge National Laboratory

View shared research outputs
Researchain Logo
Decentralizing Knowledge