A Neutral Beam Injector Upgrade for NSTX

Stevenson, T. ; McCormack, B ; Loesser, G.D. ; Kalish, M. ; Ramakrishnan, S. ; Grisham, L. ; Edwards, J. ; Cropper, M. ; Rossi, G. ; Halle, A. von ; Williams, M.

Princeton University. Plasma Physics Laboratory.

关键词: Blowers;    Ion Sources;    Impingement;    Neutral Particles;    70 Plasma Physics And Fusion Technology;   

DOI  :  10.2172/793023
RP-ID  :  PPPL-3651
RP-ID  :  AC02-76CH03073
RP-ID  :  793023

美国|英语

来源: UNT Digital Library

【 摘 要 】

The National Spherical Torus Experiment (NSTX) capability with a Neutral Beam Injector (NBI) capable of 80 kiloelectronvolt (keV), 5 Megawatt (MW), 5 second operation. This 5.95 million dollar upgrade reused a previous generation injector and equipment for technical, cost, and schedule reasons to obtain these specifications while retaining a legacy capability of 120 keV neutral particle beam delivery for shorter pulse lengths for possible future NSTX experiments. Concerns with NBI injection included power deposition in the plasma, aiming angles from the fixed NBI fan array, density profiles and beam shine through, orbit losses of beam particles, and protection of the vacuum vessel wall against beam impingement. The upgrade made use of the beamline and cryo panels from the Neutral Beam Test Stand facility, existing power supplies and controls, beamline components and equipment not contaminated by tritium during DT [deuterium-tritium] experiments, and a liquid Helium refrigerator plant to power and cryogenically pump a beamline and three ion sources. All of the Tokamak Fusion Test Reactor (TFTR) ion sources had been contaminated with tritium, so a refurbishment effort was undertaken on selected TFTR sources to rid the three sources destined for the NSTX NBI of as much tritium as possible. An interconnecting duct was fabricated using some spare and some new components to attach the beamline to the NSTX vacuum vessel. Internal vacuum vessel armor using carbon tiles was added to protect the stainless steel vacuum vessel from beam impingement in the absence of plasma and interlock failure. To date, the NBI has operated to 80 keV and 5 MW and has injected requested power levels into NSTX plasmas with good initial results, including high beta and strong heating characteristics at full rated plasma current.