Analysis of divertor plasma in ohmically and neutral beam heated hydrogen discharges in JT-60
Creators
- 1. Japan Atomic Energy Research Inst., Naka, Ibaraki. Naka Fusion Research Establishment
Description
The characteristics of ohmically and high power neutral beam heated (PNBI ∼ 20 MW) hydrogen divertor plasmas in JT-60 are analysed on the basis of a plasma fluid model. The calculated radiation loss of the divertor plasma and the density dependence of the neutral pressure in the divertor chamber (PH2div varies as to n-bare2) are qualitatively in good agreement with the experimental results. The divertor radiation loss in ohmically heated discharges can be explained by hydrogen line radiation and impurity radiation. The higher neutral pressure in neutral beam heated discharges can be explained by the decrease of the global particle confinement time in comparison with that in ohmically heated discharges. (author). Letter-to-the-editor. 26 refs, 7 figs, 1 tab
Additional details
Publishing Information
- Journal Title
- Nucl. Fusion
- Journal Volume
- 28
- Journal Issue
- 2
- Series
- Nucl. Fusion.
- Journal Page Range
- 318-323
- ISSN
- 0029-5515
- CODEN
- NUFUA
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 19047840
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BEAM INJECTION HEATING; CONFINEMENT TIME; DIVERTORS; ENERGY LOSSES; HYDROGEN; IMPURITIES; JOULE HEATING; JT-60 TOKAMAK; NEUTRAL ATOM BEAM INJECTION; PLASMA
- Descriptors DEC
- BEAM INJECTION; CLOSED PLASMA DEVICES; ELEMENTS; HEATING; NONMETALS; PLASMA HEATING; THERMONUCLEAR DEVICES; TOKAMAK DEVICES
Optional Information
- Collaborations
- JT-60 Team.