Aluminum limiter experiment in ST tokamak
Abstract
In order to investigate the effects of a light-element limiter on plasma parameters, aluminum rail limiters interchangeable with Mo rails were installed top, bottom, and outside directions in the ST tokamak. The inside limiter remained a fixed Mo rail. Compared with discharges produced immediately before and after with the usual Mo limiters, the ''aluminum'' discharges showed an increase of T/sub e/ (by factors of 1.4-2 near the center) and of energy confinement (by factors of 2 to 3 in el. energy/power input, depending on time of observation). H/sub 2/ and He discharges showed practically identical effects. In plasma composition, the Mo concentration dropped significantly, but Fe only slightly if at all; the Al concentration was about 3-5 percent (i.e., large compared to the heavier metals), whereas oxygen, about 4 to 8 percent to start with, dropped to insignificance, probably as a result of Al evaporation. The z/sub eff/ from resistivity increased 20-30 percent although the resistance dropped because of the higher T/sub e/. The improved T/sub e/ and energy confinement are thought to be the result of cumulative effects of more favorable radial current and power input distributions rather than direct energy losses by radiation.
- Authors:
- Publication Date:
- Research Org.:
- Princeton Univ., N.J. (USA). Plasma Physics Lab.
- Sponsoring Org.:
- US Energy Research and Development Administration (ERDA)
- OSTI Identifier:
- 7363005
- Report Number(s):
- MATT-1203
TRN: 76-015964
- DOE Contract Number:
- E(11-1)-3073
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ST TOKAMAK; LIMITERS; ALUMINIUM; ELECTRIC DISCHARGES; ENERGY LOSSES; MOLYBDENUM; PLASMA CONFINEMENT; CLOSED PLASMA DEVICES; CONFINEMENT; ELEMENTS; METALS; REFRACTORY METALS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; TRANSITION ELEMENTS; 700209* - Fusion Power Plant Technology- Component Development & Materials Testing
Citation Formats
Meservey, E. B., Bretz, N., Dimock, D. L., and Hinnov, E. Aluminum limiter experiment in ST tokamak. United States: N. p., 1976.
Web. doi:10.2172/7363005.
Meservey, E. B., Bretz, N., Dimock, D. L., & Hinnov, E. Aluminum limiter experiment in ST tokamak. United States. doi:10.2172/7363005.
Meservey, E. B., Bretz, N., Dimock, D. L., and Hinnov, E. Thu .
"Aluminum limiter experiment in ST tokamak". United States.
doi:10.2172/7363005. https://www.osti.gov/servlets/purl/7363005.
@article{osti_7363005,
title = {Aluminum limiter experiment in ST tokamak},
author = {Meservey, E. B. and Bretz, N. and Dimock, D. L. and Hinnov, E.},
abstractNote = {In order to investigate the effects of a light-element limiter on plasma parameters, aluminum rail limiters interchangeable with Mo rails were installed top, bottom, and outside directions in the ST tokamak. The inside limiter remained a fixed Mo rail. Compared with discharges produced immediately before and after with the usual Mo limiters, the ''aluminum'' discharges showed an increase of T/sub e/ (by factors of 1.4-2 near the center) and of energy confinement (by factors of 2 to 3 in el. energy/power input, depending on time of observation). H/sub 2/ and He discharges showed practically identical effects. In plasma composition, the Mo concentration dropped significantly, but Fe only slightly if at all; the Al concentration was about 3-5 percent (i.e., large compared to the heavier metals), whereas oxygen, about 4 to 8 percent to start with, dropped to insignificance, probably as a result of Al evaporation. The z/sub eff/ from resistivity increased 20-30 percent although the resistance dropped because of the higher T/sub e/. The improved T/sub e/ and energy confinement are thought to be the result of cumulative effects of more favorable radial current and power input distributions rather than direct energy losses by radiation.},
doi = {10.2172/7363005},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 1976},
month = {Thu Jan 01 00:00:00 EST 1976}
}
-
During the first quarter, the UCLA members of the ALT-II team worked primarily on the development of the experimental program plan and the diagnostics selection, and on the data acquisition system. These programs are discussed in this report.
-
Heavy-impurity recycling at a limiter and power-loss limitation to a limiter in tokamak
Since the density of high-z impurities in tokamaks is generally observed to saturate, the heavy-impurity recycling rate is presumed to be less than unity. On this basis, plasma edge temperature is calculated to be low and an upper limit to power carried out by charged particles is estimated to be small as observed in experiment. This result suggests that the total radiation loss by low- and high-z impurities is always large in a conventional tokamak with high power input and small charge-exchange loss. -
Advanced Limiter Test-II Program to field a toroidal belt pump limiter in the TEXTOR tokamak. Progress report, FY 1985
During the first quarter, the UCLA members of the ALT-II team worked primarily on the development of the experimental program plan and the diagnostics selection, and on the data acquisition system. These programs are discussed in this report. -
Deuterium recycling, confinement, and limiter flux in TFTR (Tokamak Fusion Test Reactor)
The neutrals code DEGAS and the transport code SNAP were used to model recycling during steady state phases of Ohmic and neutral beam-heated discharges in TFTR. The flux of deuterium from the inner limiter is calculated to be 15--45 times the total D{sub {alpha}} emission rate, with {approx}2/3 of the deuterium flux resulting from D{sup +} flow in the scrape off to the limiter, and {approx}1/3 resulting from D{sup 0} scattering off the limiter. The total D{sup +} ionization rate in the core plasma is 6--24 times the total D{sub {alpha}} emission rate, and is larger than the total neutralmore »