학술논문

Status and Plans for the National Spherical Torus Experimental Research Facility
Document Type
Journal Article
Author
A. C. SontagA. FieldA. GlasserA. K. RamA. L. RoquemoreA. PigarovA. Von HalleB. A. NelsonB. C. StrattonB. P. LeBlancC. BourdelleC. BushC. DomierC. H. SkinnerC. JunC. K. PhillipsC. KesselC. NeumeyerC. S. ChangD. A. GatesD. HumphreysD. MastravitoD. MuellerD. PacellaD. R. SmithD. RasmussenD. S. DarrowD. StotlerD. StutmanD. W. JohnsonD. W. SwainE. D. FredricksonE. FreddE. MazzucatoE. PerryE. RuskovE. SynakowskiF. M. LevintonG. A. WurdenG. D. PorterG. GettelfingerG. LabikG. OliaroG. RewoldtG. TaylorG. Y. FuH. K. ParkH. SchneiderH. W. KugelI. SemenovI. ZatzJ. BoedoJ. C. HoseaJ. ChrzanowskiJ. FoleyJ. H. KimJ. LawsonJ. LowranceJ. M. BialekJ. ManickamJ. MenardJ. R. FerronJ. R. WilsonJ. RobinsonJ. SchmidtJ. TimberlakeJ. WilgenK. C. LeeK. L. TritzK. ShaingK. ShinoharaK. W. HillL DudekL. GuazzottoL. L. LaoL. R. GrishamM. BitterM. D. CarterM. FinkenthalM. G. BellM. KalishM. M. MenonM. NagataM. RediM. SchafferM. WadeM. WilliamsMasayuki OnoN. C. LuhmannN. GorelenkovN. NishinoO. MitaraiP. BeiersdorferP. C. EfthimionP. HeitzenroederP. M. RyanP. RoneyP. SichtaP. T. BonoliR. AkersR. E. BellR. EllisR. FederR. HarveyR. HatcherR. J. GoldstonR. J. HawrylukR. KaitaR. MaingiR. MaquedaR. MarsalaR. ParsellsR. PinskerR. RamanR. WoolleyS. A. SabbaghS. BernabeiS. F. PaulS. G. LeeS. J. DiemS. J. ZwebenS. KrasheninnikovS. KubotaS. M. KayeS. RamakrishnanS. S. MedleyT. BigelowT. GibneyT. K. MauT. M. BiewerT. MunsatT. PeeblesT. R. JarboeT. StevensonV. SoukhanovskiiW. BlanchardW. ChoeW. DavisW. HeidbrinkW. HoulbergW. R. WamplerW. ZhuX. TangX. XuY. TakaseY.-K. M. PengZ. Wang
Source
IEEJ Transactions on Fundamentals and Materials. 2005, 125(11):868
Subject
NSTX
magnetic fusion
spherical torus
Language
English
ISSN
0385-4205
1347-5533
Abstract
An overview of the research capabilities and the future plans on the MA-class National Spherical Torus Experiment (NSTX) at Princeton is presented. NSTX research is exploring the scientific benefits of modifying the field line structure from that in more conventional aspect ratio devices, such as the tokamak. The relevant scientific issues pursued on NSTX include energy confinement, MHD stability at high β, non-inductive sustainment, solenoid-free start-up, and power and particle handling. In support of the NSTX research goal, research tools are being developed by the NSTX team. In the context of the fusion energy development path being formulated in the US, an ST-based Component Test Facility (CTF) and, ultimately a high β Demo device based on the ST, are being considered. For these, it is essential to develop high performance (high β and high confinement), steady-state (non-inductively driven) ST operational scenarios and an efficient solenoid-free start-up concept. We will also briefly describe the Next-Step-ST (NSST) device being designed to address these issues in fusion-relevant plasma conditions.