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Title: Direct Observation of IBW Induced Poloidal Flow in TFTR

Abstract

Shearing of the plasma poloidal rotation velocity was observed during application of ion Bernstein wave IBW) power in the Tokamak Fusion Test Reactor (TFTR) tokamak. The first evidence of corroboration between measured poloidal velocity shearing and actively induced Reynolds stress effects is presented. A model reproduces salient experimental features: The observed sheared flow occurs near the tritium fifth harmonic cyclotron resonance layer and depends strongly on the tritium density, in agreement with the model. Furthermore, the model reproduces the observed insensitivity of the induced rotation to the tritium density in the region between the third deuterium harmonic layer and the fifth tritium harmonic layer.

Authors:
; ; ; ; ;
Publication Date:
Research Org.:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
2378
Report Number(s):
PPPL-3320
ON: DE00002378
DOE Contract Number:
AC02-76CH03073
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION; TFTR Tokamak; Mathematical Models; Shear; Ion Waves; Flow Stress

Citation Formats

Bell, R.E., Bernabei, S., Hosca, J.C., LeBlanc, B.P., Majeski, R., and et al. Direct Observation of IBW Induced Poloidal Flow in TFTR. United States: N. p., 1998. Web. doi:10.2172/2378.
Bell, R.E., Bernabei, S., Hosca, J.C., LeBlanc, B.P., Majeski, R., & et al. Direct Observation of IBW Induced Poloidal Flow in TFTR. United States. doi:10.2172/2378.
Bell, R.E., Bernabei, S., Hosca, J.C., LeBlanc, B.P., Majeski, R., and et al. Sun . "Direct Observation of IBW Induced Poloidal Flow in TFTR". United States. doi:10.2172/2378. https://www.osti.gov/servlets/purl/2378.
@article{osti_2378,
title = {Direct Observation of IBW Induced Poloidal Flow in TFTR},
author = {Bell, R.E. and Bernabei, S. and Hosca, J.C. and LeBlanc, B.P. and Majeski, R. and et al.},
abstractNote = {Shearing of the plasma poloidal rotation velocity was observed during application of ion Bernstein wave IBW) power in the Tokamak Fusion Test Reactor (TFTR) tokamak. The first evidence of corroboration between measured poloidal velocity shearing and actively induced Reynolds stress effects is presented. A model reproduces salient experimental features: The observed sheared flow occurs near the tritium fifth harmonic cyclotron resonance layer and depends strongly on the tritium density, in agreement with the model. Furthermore, the model reproduces the observed insensitivity of the induced rotation to the tritium density in the region between the third deuterium harmonic layer and the fifth tritium harmonic layer.},
doi = {10.2172/2378},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Nov 01 00:00:00 EST 1998},
month = {Sun Nov 01 00:00:00 EST 1998}
}

Technical Report:

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  • Shearing of the plasma poloidal rotation velocity was observed during application of ion Bernstein wave power in the Tokamak Fusion Test Reactor. The first evidence of corroboration between measured poloidal velocity shearing and actively induced Reynolds stress effects is presented. A model reproduces salient experimental features: The observed sheared flow occurs near the tritium fifth harmonic cyclotron resonance layer and depends strongly on the tritium density in agreement with the model. Furthermore, the model reproduces the observed insensitivity of the induced rotation to the tritium density in the region between the third deuterium harmonic layer and the fifth tritium harmonicmore » layer. {copyright} {ital 1999} {ital The American Physical Society}« less
  • Recent operation of the Tokamak Fusion Test Reactor TFTR, has produced plasma equilibria with values of {Lambda} {triple bond} {beta}{sub p eq} + l{sub i}/2 as large as 7, {epsilon}{beta}{sub p dia} {triple bond} 2{mu}{sub 0}{epsilon}/{much lt}B{sub p}{much gt}{sup 2} as large as 1.6, and Troyon normalized diamagnetic beta, {beta}{sub N dia} {triple bond} 10{sup 8}<{beta}{sub t}{perpendicular}>aB{sub 0}/I{sub p} as large as 4.7. When {epsilon}{beta}{sub p dia} {approx gt} 1.25, a separatrix entered the vacuum chamber, producing a naturally diverted discharge which was sustained for many energy confinement times, {tau}{sub E}. The largest values of {epsilon}{beta}{sub p} and plasma storedmore » energy were obtained when the plasma current was ramped down prior to neutral beam injection. The measured peak ion and electron temperatures were as large as 24 keV and 8.5 keV, respectively. Plasma stored energy in excess of 2.5 MJ and {tau}{sub E} greater than 130 msec were obtained. Confinement times of greater than 3 times that expected from L-mode predictions have been achieved. The fusion power gain. Q{sub DD}, reached a values of 1.3 {times} 10{sup {minus}3} in a discharge with I{sub p} = 1 MA and {epsilon}{beta}{sub p dia} = 0.85. A large, sustained negative loop voltage during the steady state portion of the discharge indicates that a substantial non-inductive component of I{sub p} exists in these plasmas. Transport code analysis indicates that the bootstrap current constitutes up to 65% of I{sup p}. Magnetohydrodynamic (MHD) ballooning stability analysis shows that while these plasmas are near, or at the {beta}{sub p} limit, the pressure gradient in the plasma core is in the first region of stability to high-n modes. 24 refs., 10 figs.« less
  • Impurity poloidal rotation velocities have been measured in the core of TFTR plasmas using a new spectroscopic diagnostic. Two types of transitions to enhanced confinement in reversed shear plasmas are examined. A bifurcation in carbon poloidal rotation is observed to occur before the transition to enhanced confinement for one of these types, while other measured plasmas parameters remain constant. A narrow radial region with reversed poloidal rotation and rotational shear is established 60-100 ms before the transition, and is associated with a large negative radial electric field.
  • Deuterium-tritium plasmas with enhanced energy confinement and stability have been produced in the high poloidal beta, advanced tokamak regime in TFTR. Confinement enhancement H {triple_bond} {tau}{sub E}/{tau}{sub E ITER-89P} > 4 has been obtained in a limiter H-mode configuration at moderate plasma current I{sub p} = 0.85 {minus} 1.46 MA. By peaking the plasma current profile, {beta}{sub N dia} {triple_bond} 10{sup 8} < {beta}{sub t{perpendicular}} > aB{sub 0}/I{sub p} = 3 has been obtained in these plasma,s exceeding the {beta}{sub N} limit for TFTR plasmas with lower internal inductance, l{sub i}. Fusion power exceeding 6.7 MW with a fusion powermore » gain Q{sub DT} = 0.22 has been produced with reduced alpha particle first orbit loss provided by the increased l{sub i}.« less
  • In Part I a visual study of an annular two-phase closed thermosyphon (wickless heat pipe) is reported. The heat transfer surface was stainless steel. Working fluids were Freon-113, ethanol, and water. Photographs of pertinent phenomena are included. The visual observations were used to interpret the measured heat transfer characteristics. For small and intermediate liquid fill quantities four flow regimes were observed in the evaporation section, in addition to nucleate boiling in the liquid pool: (1) a smooth continuous film with surface evaporation; (2) breakdown of the film into stable rivulets; (3) a wavy film with unstable rivulets; and (4) amore » wavy film with bubble nucleation in the unstable rivulets. Three different types of 'dry-out' conditions (heat transfer limits) were also observed and are reported in detail. In Part II results obtained for a stainless steel tubular opaque device with Freon-113 as a working fluid are reported. This device was designed to permit a larger range of geometric configurations (heated length, adiabatic length, cooled length, and angle of inclination). Both steady state heat transfer characteristics and heat transfer limits are reported in detail. In Part III, results from the visual and opaque devices are compared and discussed. The present results are compared with those of other investigations, and conclusions and recommendations are drawn.« less