A review of anticipated achievements in the light ion beam method of the inertial confinement fus... more A review of anticipated achievements in the light ion beam method of the inertial confinement fusion program is presented. They allow to estimate the cost of produced electric energy. It appears to be quite competitive to other fusion reactor designs at the 1000 MWe level and above. (AIP)
Submitted for the GEC11 Meeting of The American Physical Society Optimization and Characterizatio... more Submitted for the GEC11 Meeting of The American Physical Society Optimization and Characterization of a Helicon Ion Source on an Inertial Electrostatic Confinement Device for Helium-3 Fusion GABRIEL BECERRA, GERALD KULCINSKI, JOHN SANTARIUS, University of WisconsinMadison — HELIOS is an inertial electrostatic confinement (IEC) fusion device designed for 3He-3He fusion studies as part of the advanced fuels program at the University of Wisconsin [1]. HELIOS uses a helicon plasma as a source of ions, which are subsequently accelerated radially to fusion energies by the electrostatic field between the spherical chamber wall and a concentric cathode grid. The experimental setup, in which 3He-3He fusion in an IEC system has previously been demonstrated, has since been upgraded to raise fusion rates to allow for diagnostic studies of IEC physics with helium-3 fuel, in order to benchmark the single-atomicspecies formalism of a numerical code on spherically convergent ion flow [2]. The helic...
A magnetic deflection-energy analyzer and Faraday trap diagnostic have been used to make measurem... more A magnetic deflection-energy analyzer and Faraday trap diagnostic have been used to make measurements of divergent deuterium anion flow in the inertial electrostatic confinement experiment at the University of Wisconsin-Madison (UW-IEC) [J. F. Santarius, G. L. Kulcinski, R. P. Ashley, D. R. Boris, B. B. Cipiti, S. K. Murali, G. R. Piefer, R. F. Radel, I. E. Radel, and A. L. Wehmeyer, Fusion Sci. Technol. 47, 1238 (2005)], a device to confine high-energy light ions in a spherically symmetric electrostatic potential well. Deuterium anion current densities as high as 8.5 microA/cm2 have been measured at the wall of the UW-IEC device, 40 cm from the surface of the device cathode with a detector assembly of admittance area 0.7 cm2. Energy spectra obtained using a magnetic deflection-energy analyzer diagnostic indicate the presence of D2(-), and D- ions produced through thermal electron attachment near the device cathode, as well as D- ions produced via charge-transfer processes between the anode and cathode of the device.
WITAMIR-I, a teandem mirror reactor, is a study by the University of Wisconsin fusion engineering... more WITAMIR-I, a teandem mirror reactor, is a study by the University of Wisconsin fusion engineering design group. Various engineering aspects and physics considerations are presented. WITAMIR-I is a high Q device with particularly attractive maintenance features and blanket characteristics.
The design of a low power (6.8 MW) tandem mirror technology test facility is given. The facility ... more The design of a low power (6.8 MW) tandem mirror technology test facility is given. The facility is based on physics presently in hand or that should be available by 1985. Technologies employed by TASKA-M are at the mid-1980's level and the device is designed to achieve a peak ...
This is the final report of a panel set up by the U.S. Department of Energy (DOE) Fusion Energy S... more This is the final report of a panel set up by the U.S. Department of Energy (DOE) Fusion Energy Sciences Advisory Committee (FESAC) in response to a charge letter from Dr. James Decker, Acting Director of the DOE Office of Science. In that letter, Dr. Decker asked FESAC to consider “whether the Fusion Energy Sciences program should broaden its scope
A review of anticipated achievements in the light ion beam method of the inertial confinement fus... more A review of anticipated achievements in the light ion beam method of the inertial confinement fusion program is presented. They allow to estimate the cost of produced electric energy. It appears to be quite competitive to other fusion reactor designs at the 1000 MWe level and above. (AIP)
Submitted for the GEC11 Meeting of The American Physical Society Optimization and Characterizatio... more Submitted for the GEC11 Meeting of The American Physical Society Optimization and Characterization of a Helicon Ion Source on an Inertial Electrostatic Confinement Device for Helium-3 Fusion GABRIEL BECERRA, GERALD KULCINSKI, JOHN SANTARIUS, University of WisconsinMadison — HELIOS is an inertial electrostatic confinement (IEC) fusion device designed for 3He-3He fusion studies as part of the advanced fuels program at the University of Wisconsin [1]. HELIOS uses a helicon plasma as a source of ions, which are subsequently accelerated radially to fusion energies by the electrostatic field between the spherical chamber wall and a concentric cathode grid. The experimental setup, in which 3He-3He fusion in an IEC system has previously been demonstrated, has since been upgraded to raise fusion rates to allow for diagnostic studies of IEC physics with helium-3 fuel, in order to benchmark the single-atomicspecies formalism of a numerical code on spherically convergent ion flow [2]. The helic...
A magnetic deflection-energy analyzer and Faraday trap diagnostic have been used to make measurem... more A magnetic deflection-energy analyzer and Faraday trap diagnostic have been used to make measurements of divergent deuterium anion flow in the inertial electrostatic confinement experiment at the University of Wisconsin-Madison (UW-IEC) [J. F. Santarius, G. L. Kulcinski, R. P. Ashley, D. R. Boris, B. B. Cipiti, S. K. Murali, G. R. Piefer, R. F. Radel, I. E. Radel, and A. L. Wehmeyer, Fusion Sci. Technol. 47, 1238 (2005)], a device to confine high-energy light ions in a spherically symmetric electrostatic potential well. Deuterium anion current densities as high as 8.5 microA/cm2 have been measured at the wall of the UW-IEC device, 40 cm from the surface of the device cathode with a detector assembly of admittance area 0.7 cm2. Energy spectra obtained using a magnetic deflection-energy analyzer diagnostic indicate the presence of D2(-), and D- ions produced through thermal electron attachment near the device cathode, as well as D- ions produced via charge-transfer processes between the anode and cathode of the device.
WITAMIR-I, a teandem mirror reactor, is a study by the University of Wisconsin fusion engineering... more WITAMIR-I, a teandem mirror reactor, is a study by the University of Wisconsin fusion engineering design group. Various engineering aspects and physics considerations are presented. WITAMIR-I is a high Q device with particularly attractive maintenance features and blanket characteristics.
The design of a low power (6.8 MW) tandem mirror technology test facility is given. The facility ... more The design of a low power (6.8 MW) tandem mirror technology test facility is given. The facility is based on physics presently in hand or that should be available by 1985. Technologies employed by TASKA-M are at the mid-1980's level and the device is designed to achieve a peak ...
This is the final report of a panel set up by the U.S. Department of Energy (DOE) Fusion Energy S... more This is the final report of a panel set up by the U.S. Department of Energy (DOE) Fusion Energy Sciences Advisory Committee (FESAC) in response to a charge letter from Dr. James Decker, Acting Director of the DOE Office of Science. In that letter, Dr. Decker asked FESAC to consider “whether the Fusion Energy Sciences program should broaden its scope
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Papers by Gerald Kulcinski