Published January 1990 | Version v1
Report

Radiation losses and global power balance of JT-60 plasmas

  • 1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

Description

Radiation losses and global power balances of the plasmas in the NB heated limiter, outer and lower X-point configurations with TiC coated Molybdenum or graphite first wall have been investigated by bolometric measurements, thermocouples and IRTV camera. Very low radiation losses of the main plasma, 10% of the absorbed power, are realized in NB heated outer X-point discharges with TiC coated molybdenum wall. In the improved divertor confinement (IDC) regime radiation loss from the divertor region increases up to 40% of the absorbed power with the line averaged electron density. That of the main plasma is approximately 20% for any electron density. Intense remote radiative cooling is realized in IDC which reduces the heat load onto divertor plates. (author). 7 refs, 11 figs

Part of:
Impurity control in toroidal devices

Additional details

Publishing Information

Imprint Title
Impurity control in toroidal devices
Imprint Pagination
173 p.
Journal Page Range
p. 145-151.
Report number
IAEA-TECDOC--536

Conference

Title
Technical committee on impurity control.
Dates
13-15 Feb 1989.
Place
Naka-Gun (Japan).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
21025514
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BEAM INJECTION HEATING; DIVERTORS; GRAPHITE; JT-60 TOKAMAK; LIMITERS; MOLYBDENUM; NEUTRAL ATOM BEAM INJECTION; POWER LOSSES; RADIATIVE COOLING; THERMONUCLEAR REACTOR WALLS
Descriptors DEC
BEAM INJECTION; CARBON; CLOSED PLASMA DEVICES; COOLING; ELEMENTS; HEATING; METALS; NONMETALS; PLASMA HEATING; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; TRANSITION ELEMENTS

Optional Information

Collaborations
JT-60 Team.