TJ-II:Impurity density and potential asymmetries: Difference between revisions

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== Description of required resources ==
== Description of required resources ==
Required resources:
 
* Number of plasma discharges or days of operation:
The required signals to perform the analysis are:
* Essential diagnostic systems:
 
* Type of plasmas (heating configuration):
* The time evolution of the plasma emissivity radial profile via tomographic reconstructions of the bolometry system signals.
* Specific requirements on wall conditioning if any:
* The time evolution of the plasma floating potential at the outer core region (<math>r/a\sim 0.9</math>).
* External users: need a local computer account for data access: yes/no
* The time evolution of the line-averaged density <math>\left<n_e(t)\right></math> with interferometry.
* Any external equipment to be integrated? Provide description and integration needs:
* The radial profiles of electron density <math>n_{e}(r, t_0)</math> and temperature at one time instant <math>t_0</math> using Thomson Scattering (TS).
* The time evolution of the electron temperature profile <math>T_{e}(r,t)</math> with Electron Cyclotron Emission (ECE), when available, calibrated with TS.
* The time evolution of the ion temperature in the core and in an outer radial position <math>T_i(r/a\sim 0.2,t)</math> and <math>T_i(r/a\sim 0.8,t)</math> with the Neutral Particle Analyzer (NPA).
* The time evolution of the radial electric field at the mid-outer resion (<math>r/a\sim 0.7-0.8</math>) with reflectometry.
* The time evolution of the electrostatic potential in the mid-outer region <math>\Phi(r/a\sim0.7,t)</math> with the double Heavy Ion Beam Probe (HIBP).
 
Other constraints regarding the desired experimental conditions are:  
 
* Good reproducibility of the plasma discharges to allow comparison across impurities and <math>Z</math>. Scannig <math>T_e</math> is also considered by the application of different ECH injected power.
* Good stationarity of plasma parameters, hence preferably ECRH plasmas, at the instant where the impurities are injected in order to extract the stationary background emissivity from that produced by the injected impurity.


== Preferred dates and degree of flexibility ==
== Preferred dates and degree of flexibility ==

Revision as of 16:49, 24 January 2017

Experimental campaign

2017 Spring

Proposal title

Impurity density and potential asymmetries

Name and affiliation of proponent

Jose M García Regaña

Description of the activity, including motivation/objectives and experience of the proponent (typically one-two pages)

Neoclassical theory predicts a non-constant portion of the electrostatic potential over the flux surfaces [1], usually denoted by , with and the poloidal and toroidal angular coordinates. When this is taken into account the equilibrium density of the different species a present in the plasma varies according to their adiabatic response and can be written as: Failed to parse (syntax error): {\displaystyle n_{a0}=\left<n\right>\exp\left(-Z_{a}e\Phi_1/T_{a}\right)} , with Failed to parse (syntax error): {\displaystyle \left<...\right>} the flux-surface-average. In TJ-II plasmas experiments and simulations [2] [3] [4] have shown that can take values from to . Variations are predicted to be larger at the outer radii than at the inner core, and stronger in ECRH plasmas than in NBI plasmas. Under conditions with large the impurities of moderate to high should experience strong variations of their densities over the flux surfaces, increasing with . These, in turn, should result in an anisotropic radiation over each flux surface and consequently a radially asymmetric radiation pattern should follow.

In the present experiment the analysis of the radial profiles and time evolution of the plasma emissivity using the TJ-II bolometry system [5] after the inyection of some selected impurities by gas puffing is proposed. The experiment aims at studying the above-mentioned link between the radially assymetric emissivity and the measured and predicted . The measurement and evolution of will be tracked during the discharges using the duplicated Langmuir probe system plasma floating potential measurements. Numerical calculations of will be carried out with the neoclassical version of the code EUTERPE at different radial locations. The application of fluid tools is also foreseen for the comparison between simulations and with the experimental results.

Description of required resources

The required signals to perform the analysis are:

  • The time evolution of the plasma emissivity radial profile via tomographic reconstructions of the bolometry system signals.
  • The time evolution of the plasma floating potential at the outer core region ().
  • The time evolution of the line-averaged density Failed to parse (syntax error): {\displaystyle \left<n_e(t)\right>} with interferometry.
  • The radial profiles of electron density and temperature at one time instant using Thomson Scattering (TS).
  • The time evolution of the electron temperature profile with Electron Cyclotron Emission (ECE), when available, calibrated with TS.
  • The time evolution of the ion temperature in the core and in an outer radial position and with the Neutral Particle Analyzer (NPA).
  • The time evolution of the radial electric field at the mid-outer resion () with reflectometry.
  • The time evolution of the electrostatic potential in the mid-outer region with the double Heavy Ion Beam Probe (HIBP).

Other constraints regarding the desired experimental conditions are:

  • Good reproducibility of the plasma discharges to allow comparison across impurities and . Scannig is also considered by the application of different ECH injected power.
  • Good stationarity of plasma parameters, hence preferably ECRH plasmas, at the instant where the impurities are injected in order to extract the stationary background emissivity from that produced by the injected impurity.

Preferred dates and degree of flexibility

Preferred dates: (format dd-mm-yyyy)

References

  1. H. Mynick Calculation of the poloidal ambipolar field in a stellarator and its effect on transport Phys. Fluids 27(8) 2086 (1984)
  2. M A Pedrosa et al., Electrostatic potential variations along flux surfaces in stellarators Nucl. Fusion 55 052001 (2015)
  3. B Liu et al. Direct experimental evidence of potential asymmetry in magnetic flux surfaces in stellarators to be submitted (2017)
  4. J M Garcı́a-Regaña et al. Electrostatic potential variation on the flux surface and its impact on impurity transport Nuclear Fusion submitted (2017)
  5. M. A. Ochando et al. Up-down and in-out asymmetry monitoring based on broadband radiation detectors Fusion Sci. and Technol. 50 313 (2006)

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