Results 11 to 20 of about 728 (184)

Development of a plasma shape and position display system for damavand tokamak control room [PDF]

مجله علوم و فنون هسته‌ای, 2023
Determining the magnetic field profile is very important for studying flux surfaces, elongation, plasma boundaries, and real-time control in tokamaks. In this research, a system for calculating and displaying the shape, position, and boundary of plasma ...
D. Iraji, H. Rasouli, Ch. Rasouli, B. Pourshahab   +3 more
doaj   +1 more source

The physics of an ignited tokamak [PDF]

Fusion Engineering and Design, 1991
A next step device which can demonstrate long burn with a high probability of success is possible, without speculating on the accumulation of favorable effects and ignoring the other ones. From the data base available today this appears possible only with large devices such as NET, ITER or JIT.
openaire   +1 more source

A model of multi-pass absorption of external EC radiation at initial stage of discharge in ITER

EPJ Web of Conferences, 2015
A model is developed for multi-pass absorption of external electron cyclotron radiation (ECR) in tokamaks, which is used at initial stage of discharge to overcome the impurity radiation barrier (burn-through). Model is based on a semi-analytical solution
Minashin P.V., Kukushkin A.B., Khayrutdinov R.R., Lukash V.E.   +3 more
doaj   +1 more source

Physics of advanced tokamaks [PDF]

Plasma Physics and Controlled Fusion, 1997
Significant reductions in the size and cost of a fusion power plant core can be realized if simultaneous improvements in the energy replacement time, , and the plasma pressure or beta, can be achieved in steady-state conditions with high self-driven, bootstrap current fraction. Significant recent progress has been made in experimentally achieving these
openaire   +1 more source

Spectroscopic diagnostics of superthermal electrons with high-number harmonic EC radiation in tokamak reactor plasmas

EPJ Web of Conferences, 2015
A method of spectroscopic diagnostics of the average perpendicular-to-magnetic-field momentum of the superthermal component of the electron velocity distribution (EVD), based on the high-number-harmonic electron cyclotron (EC) radiation, is suggested for
Minashin P.V., Kukushkin A.B.
doaj   +1 more source

Cost Assessment of a Tokamak Fusion Reactor with an Inventive Method for Optimum Build Determination

Energies, 2021
An inventive method was applied to determine the minimum major radius, R0, and the optimum build of a tokamak fusion reactor that simultaneously meets all physics, engineering, and neutronics constraints.
Gahyung Jo, Jae-Min Kwon, Ara Cho, Hyun-Kyung Chung, Bong-Guen Hong   +4 more
doaj   +1 more source

Physics design requirements for the Tokamak Physics Experiment (TPX) [PDF]

15th IEEE/NPSS Symposium. Fusion Engineering, 2002
The design of TPX is driven by physics requirements that follow from its mission. The tokamak and heating systems provide the performance and profile controls needed to study advanced steady state tokamak operating modes. The magnetic control systems provide substantial flexibility for the study of regimes with high beta and bootstrap current.
Neilson, G. H., Goldston, R. J., Jardin, S. C., Reiersen, W. T., Nevins, W. M., Porkolab, M., Ulrickson, M.   +6 more
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Conceptual design of the tokamak radiation shielding for the Tokamak Physics Experiment (TPX) [PDF]

15th IEEE/NPSS Symposium. Fusion Engineering, 2002
The tokamak radiation shielding includes the neutron and gamma shielding around the torus and penetrations required to (1) limit activation of components outside the shield to levels that permit hands-on maintenance and (2) limit the nuclear heating of the superconducting coils and cold structure. The primary design drivers are space, the 350/spl deg/C
M.J. Cole, B.E. Nelson, P.J. Fogarty, G.H. Jones, P.L. Goranson, Y. Gohar, S.L. Liew   +6 more
openaire   +1 more source

Optimal Radial Build and Transmutation Properties of a Fusion-Based Transmutation Reactor with Molten Salt Coolants

Energies, 2022
The optimal shape of a fusion-based transmutation reactor with a molten salt coolant was determined by plasma physics, technology, and neutronic requirements.
Bong-Guen Hong
doaj   +1 more source

Advanced tokamak physics in DIII-D [PDF]

Plasma Physics and Controlled Fusion, 2000
Advanced tokamaks seek to achieve a high bootstrap current fraction without sacrificing fusion power density or fusion gain. Good progress has been made towards the DIII-D research goal of demonstrating a high-β advanced tokamak plasma in steady state with a relaxed, fully non-inductive current profile and a bootstrap current fraction greater than 50%.
Petty, CC, Luce, TC, Politzer, PA, Wade, MR, Allen, SL, Austin, ME, Bray, B, Burrell, KH, Casper, TA, Chu, MS, Ferron, JR, Fredrickson, ED, Garofalo, AM, Gohil, P, Gorelov, I, Greenfield, CM, Heidbrink, WW, Hsieh, C-L, Hyatt, AW, Jayakumar, R, Johnson, LC, Kinsey, JE, La Haye, RJ, Lao, LL, Lasnier, CJ, Lazarus, EA, Leonard, AW, Lin-Liu, YR, Lohr, J, Mahdavi, MA, Makowski, MA, McKee, GR, Murakami, M, Navratil, GA, Okabayashi, M, Petrie, TW, Pinsker, RI, Prater, R, Rettig, CL, Rhodes, TL, Rice, BW, Scoville, JT, Staebler, GM, Strait, EJ, Taylor, TS, Watkins, JG, West, WP, Wolf, NS, Wong, K-L   +48 more
openaire   +3 more sources