FusionPapers
図版検索AI要約wiki日本の研究装置ジャーナルChatGPTAbout
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

The confinement of dilute populations of beam ions in the national spherical torus experiment

W.W. Heidbrink, M. Miah, D. Darrow, B. LeBlanc, S.S. Medley, A.L. Roquemore, F.E. Cecil2003年被引用 29Nuclear FusionIF 3出版社

Short ∼3 ms pulses of 80 keV deuterium neutrals are injected at three different tangency radii into the national spherical torus experiment. The confinement is studied as a function of tangency radius, plasma current (between 0.4 and 1.0 MA), and toroidal field (between 2.5 and 5.0 kG). The jump in neutron emission during the pulse is used to infer prompt losses of beam ions. In the absence of MHD, the neutron data show the expected dependences on beam angle and plasma current; the average jump in the neutron signal is 88±39% of the expected jump. The decay of the neutron and neutral particle signals following the blip are compared to the expected classical deceleration to detect losses on a 10 ms timescale. The temporal evolution of these signals are consistent with Coulomb scattering rates, implying an effective beam-ion confinement time ≳100 ms. The confinement is insensitive to the toroidal field despite large values of ρ∇B/B (≲0.25), so any effects of non-conservation of the adiabatic invariant μ are smaller than the experimental error.

装置

nstx-u高精度(タイトル一致)

wiki

NSTXSpherical torusBeam ion
この論文にはまだAI要約がありません。

関連論文

Characterization of fast ion behaviour during tangential neutral beam injection in the Advanced Toroidal Facility

1995Nuclear Fusion

Energetic ion confinement studies using comprehensive neutron diagnostics in the Large Helical Device

2019Nuclear Fusion

Fusion neutron production with deuterium neutral beam injection and enhancement of energetic-particle physics study in the large helical device

2018Nuclear Fusion

Investigation of beam– and wave–plasma interactions in spherical tokamak Globus-M

2011Nuclear Fusion

Thermal energy confinement scaling in PDX limiter discharges

1984Nuclear Fusion

Fast ion confinement during high power tangential neutral beam injection into low plasma current discharges on the ISX-B tokamak

1988Nuclear Fusion

Progress towards high performance plasmas in the National Spherical Torus Experiment (NSTX)

2005Nuclear Fusion

Assessment of the plasma start-up in Wendelstein 7-X with neutral beam injection

2015Nuclear Fusion

Calculation of the non-inductive current profile in high-performance NSTX plasmas

2011Nuclear Fusion

Plasma production by the trapping of energetic atoms

1960Nuclear Fusion