Title :
Beam transport code for the KSTAR NB heating system
Author :
Oh, B.H. ; Dlougach, E.D.
Author_Institution :
Korea Adv. Energy Res. Inst., Daejeon, South Korea
Abstract :
Beam transport with re-ionization (BTR) code for KSTAR neutral beam heating system has been developed 1) to describe the neutral beam production and transmission in the beam line; 2) to simulate the processes accompanying the beam transport; 3) to determine the power deposition onto the neutral beam line components; and 4) to reproduce the real operational conditions of the system in presence of magnetic fields and background gas. This code is available in calculating the beam losses along the beam line, and in obtaining the footprints of the beam at the selected cross-sections. Also it could be useful in defining the acceptable level of the residual magnetic field, and in estimating the effect of tokamak stray field on the re-ionized flux. The models and calculated results with BTR code are described in this paper.
Keywords :
Tokamak devices; beam handling equipment; beam handling techniques; particle beam dynamics; plasma beam injection heating; plasma toroidal confinement; BTR code; KSTAR neutral beam heating system; background gas; beam losses; beam transport code; beam transport with reionization code; magnetic fields; neutral beam line components; neutral beam production; neutral beam transmission; operational conditions; power deposition; reionized flux; residual magnetic field; tokamak stray field; Deuterium; Heating; Ion sources; Magnetic fields; Magnetic flux; Niobium; Power system modeling; Power system protection; Production systems; Tokamaks;
Conference_Titel :
Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on
Print_ISBN :
0-7803-7908-X
DOI :
10.1109/FUSION.2003.1426686