Search Results - "Fredd, E."
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1
A megawatt-level 28 GHz heating system for the National Spherical Torus Experiment Upgrade
Published in EPJ Web of Conferences (01-01-2015)“…The National Spherical Torus Experiment Upgrade (NSTX-U) will operate at axial toroidal fields of ≤ 1 T and plasma currents, Ip ≤ 2 MA. The development of…”
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2
Using acoustic detectors to monitor iter ich transmission lines arc events
Published in 2015 IEEE 26th Symposium on Fusion Engineering (SOFE) (01-05-2015)“…Severe and continuous arcs in transmission lines systems can be detrimental to the RF sources and the associated transmission lines. In order to prevent any…”
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3
The LHCD launcher for Alcator C-Mod—Design, construction, calibration and testing
Published in Fusion engineering and design (01-11-2005)“…MIT and PPPL have joined together to fabricate a high-power lower hybrid current drive (LHCD) system for supporting steady-state AT regime research on Alcator…”
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4
Compact power detection probe for the RF plasma heating waveguide array
Published in IEEE transactions on plasma science (01-04-2005)“…Reduced height waveguide arrays are commonly used in fusion plasma radio frequency heating in the lower hybrid frequency range. In order to distinguish the…”
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5
Engineering design of the National Spherical Torus Experiment
Published in Fusion engineering and design (01-02-2001)“…NSTX is a proof-of-principle experiment aimed at exploring the physics of the ‘spherical torus’ (ST) configuration, which is predicted to exhibit more…”
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6
Development of process equipment to separate nonthermal and thermal effects of RF energy on microorganisms
Published in The Journal of microwave power and electromagnetic energy (2000)“…We developed a modified radio frequency (RF) dielectric heater, as a component of a continuous process, for isolating thermal and nonthermal effects of RF…”
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7
Status of the ITER Ion Cyclotron H&CD system
Published in Fusion engineering and design (01-10-2013)“…► We summarize the progress and outstanding issues in the development of the ITER Ion Cyclotron Heating and Current Drive (IC H&CD) system. ► The system is…”
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8
Dynamic RF power control for DIII-D ICH/fast wave operation
Published in 2013 IEEE 25th Symposium on Fusion Engineering (SOFE) (01-06-2013)“…Thanks to the broadcast industry, high power transmitters between 10 MHz and 100 MHz in megawatts power range can be obtained at a reasonable price. Thus, we…”
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High power, high voltage FETs in linear applications: A user's perspective
Published in 2009 23rd IEEE/NPSS Symposium on Fusion Engineering (01-06-2009)“…The specifications of the current crop of high-power, high-voltage field-effect transistors (FETs) can lure a designer into employing them in high-voltage DC…”
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10
Compact probe design for power monitoring from the narrow side of the reduced height waveguide
Published in Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) (2002)“…Due to confined space in a stack of reduced height waveguides, power detection of the incident and reflected wave in the reduced height waveguide is extremely…”
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11
Improvement for lower hybrid coupler with step transformers and power dividers
Published in 20th IEEE/NPSS Symposium onFusion Engineering, 2003 (2003)“…PPPL and MIT are preparing an experiment of current profile control using lower hybrid waves in order to produce and sustain advanced tokamak regimes in steady…”
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12
Fast RF power diagnostics for the DIII-D fast wave current drive system using commercial FPGA-based systems
Published in 2013 IEEE 25th Symposium on Fusion Engineering (SOFE) (01-06-2013)“…The Fast Wave Current Drive System is used to heat and drive non-inductive current in the DIII-D tokamak plasma. The phase and power of the transmitted and…”
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13
Design status of ITER IC H&CD plant system control
Published in 2013 IEEE 25th Symposium on Fusion Engineering (SOFE) (01-06-2013)“…A functional approach has been used to define functions & responsibility sharing of each Local Control Unit (LCU) and Ion Cyclotron Heating and Current Drive…”
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14
A Medium Power ECH/EBW Heating System for NSTX
Published in 2007 IEEE 34th International Conference on Plasma Science (ICOPS) (01-06-2007)“…Summary form only given. Electron Bernstein waves (EBW) are being investigated for plasma heating and current drive of overdense plasmas on NSTX. EB emission…”
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15
Simulation results for new NSTX HHFW antenna straps design by using microwave studio
Published in 2009 23rd IEEE/NPSS Symposium on Fusion Engineering (01-06-2009)“…Experimental results have shown that the high harmonic fast wave (HHFW) at 30 MHz can provide substantial plasma heating and current drive for the NSTX…”
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16
Grounding, DC Supplies, and Controlling Signal Issues for a Tunable Reflectometry System
Published in 2007 IEEE 22nd Symposium on Fusion Engineering (01-06-2007)“…Reflectometry, which uses the microwave radar technique to probe the magnetically confined fusion plasmas, is a very powerful tool to observe the density…”
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17
Making of the NSTX facility
Published in 18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050) (1999)“…The NSTX (National Spherical Torus Experiment) facility located at Princeton Plasma Physics Laboratory is the newest national fusion science experimental…”
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18
Calibration techniques for broadband MM & SMMW diagnostic instruments
Published in 1983 Eighth International Conference on Infrared and Millimeter Waves (01-12-1983)“…Absolute calibration of electron cyclotron emission (ECE) diagnostics allows for the determination of temporal electron temperature measurements independent of…”
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19
Upgrading the General Atomics Radio-Frequency Sources for Higher Power
Published in 2007 IEEE 22nd Symposium on Fusion Engineering (01-06-2007)“…Several years ago the Princeton Plasma Physics Laboratory (PPPL), Oak Ridge National Laboratory (ORNL) and General Atomics (G.A.) formed a collaboration to…”
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20
RF Sources for the ITER Ion Cyclotron Heating and Current Drive System
Published in 21st IEEE/NPS Symposium on Fusion Engineering SOFE 05 (01-09-2005)“…The RF source requirements for the ITER ion cyclotron (IC) heating and current drive system are very challenging- 20 MW CW power into an antenna load with a…”
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