Calculations of neutral transport in the PDX divertor
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference15 articles.
1. Regime of Improved Confinement and High Beta in Neutral-Beam-Heated Divertor Discharges of the ASDEX Tokamak
2. Attainment of high confinement in neutral beam heated divertor discharges in the PDX tokamak
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3. A Monte Carlo code describing the neutral gas transport in pipe configurations with attenuating media;Journal of Computational Physics;1993-06
4. Analysis of divertor plasma in ohmically and neutral beam heated hydrogen discharges in JT-60;Nuclear Fusion;1988-02-01
5. ASDEX Edge and Divertor Simulation and the Problem of Incomplete and Inaccurate Experimental Data;Contributions to Plasma Physics;1988
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