Published September 2012 | Version v1
Report

Non-Axisymmetric Equilibrium Reconstruction for Stellarators, Reversed Field Pinches and Tokamaks

  • 1. Auburn University, Auburn (United States)
  • 2. Princeton Plasma Physics Laboratory, Princeton (United States)
  • 3. University of Wisconsin, Madison (United States)
  • 4. Consorzio RFX, EURATOM-ENEA Association, Padova (Italy)
  • 5. Oak Ridge National Laboratory, Oak Ridge (United States)
  • 6. National Institute for Fusion Science, Toki (Japan)
  • 7. General Atomics, San Diego (United States)

Description

Full text: Equilibrium reconstruction is the process of minimizing the mismatch between modeled and observed signals by changing the parameters that specify the equilibrium. While stellarator equilibria are inherently non-axisymmetric, non-axisymmetric effects are also crucial for understanding stability and confinement of high-performance reversed field pinch and tokamak plasmas. Therefore, two-dimensional reconstruction tools are not adequate for fully exploring 3D plasmas. The V3FIT and STELLOPT codes are 3D equilibrium reconstruction codes, both based on the VMEC 3D equilibrium code. VMEC models field-period symmetric 3D flux surface geometry but does not treat magnetic islands and chaotic regions. VMEC requires the specification of the pressure and either rotational transform or toroidal current profiles, as functions of either the toroidal or poloidal flux. VMEC can treat both axisymmetric and non-axisymmetric configurations, both free- and fixed-boundary equilibria, and both stellarator-symmetric and non-stellarator-symmetric equilibria. Both V3FIT and STELLOPT can utilize signals from magnetic diagnostics, soft X-rays (SXR), Thomson scattering, and geometrical information from plasma limiters. STELLOPT can also utilize Motional Stark Effect (MSE) signals. Both calculate a finite difference approximation to a Jacobian for the signal-mismatch minimization. V3FIT and STELLOPT differ in the details of their minimization algorithms, their utilization of auxiliary profiles (like electron density and soft x-ray emissivity), and in their computation of model signals. V3FIT is currently in use on stellarators (HSX, CTH), reversed field pinches (RFX-mod) and tokamaks (DIII-D) for a wide variety of studies: interpretation of Pfirsch-Schliiter and bootstrap currents, design of new magnetic diagnostics, magnetic island generation, vertical instabilities, density-limit disruption activity, conformance of multiple data sources to a single set of flux surfaces, quasi-single helicity states in reversed field pinches, and error-field effects on nominally axisymmetric tokamak plasmas. STELLOPT is currently in use on stellarators (LHD) and tokamaks (DIII-D) providing detailed profile reconstructions for transport calculations and diagnostic inversions. Examples of equilibrium reconstruction are shown. (author)

Part of:
24. IAEA Fusion Energy Conference. Programme and Book of Abstracts

Additional details

Publishing Information

Imprint Title
24. IAEA Fusion Energy Conference. Programme and Book of Abstracts
Imprint Pagination
789 p.
Journal Page Range
p. 285
Report number
IAEA-CN--197

Conference

Title
24. IAEA Fusion Energy Conference
Acronym
FEC 2012
Dates
8-13 Oct 2012
Place
San Diego, CA (United States)

Optional Information

Secondary number(s)
TH/7--2