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Error field measurement, correction and heat flux balancing on Wendelstein 7-X

Journal Article · · Nuclear Fusion
 [1];  [2];  [2];  [3];  [4];  [2];  [2];  [2];  [2];  [5];  [5];  [2];  [2];  [1]
  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. Max Planck Inst. for Plasma Physics, Greifswald (Germany)
  3. Columbia Univ., New York, NY (United States)
  4. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  5. Wigner Research Center for Physics, Budapest (Hungary)
The measurement and correction of error fields in Wendelstein 7-X (W7-X) is critical to long pulse high beta operation, as small error fields may cause overloading of divertor plates in some configurations. Accordingly, as part of a broad collaborative effort, the detection and correction of error fields on the W7-X experiment has been performed using the trim coil system in conjunction with the flux surface mapping diagnostic and high resolution infrared camera. In the early commissioning phase of the experiment, the trim coils were used to open an n/m = 1/2 island chain in a specially designed magnetic configuration. The flux surfacing mapping diagnostic was then able to directly image the magnetic topology of the experiment, allowing the inference of a small similar to 4 cm intrinsic island chain. The suspected main sources of the error field, slight misalignment and deformations of the superconducting coils, are then confirmed through experimental modeling using the detailed measurements of the coil positions. Observations of the limiters temperatures in module 5 shows a clear dependence of the limiter heat flux pattern as the perturbing fields are rotated. Plasma experiments without applied correcting fields show a significant asymmetry in neutral pressure (centered in module 4) and light emission (visible, H-alpha, CII, and CIII). Such pressure asymmetry is associated with plasma-wall (limiter) interaction asymmetries between the modules. Application of trim coil fields with n = 1 waveform correct the imbalance. Confirmation of the error fields allows the assessment of magnetic fields which resonate with the n/m = 5/5 island chain.
Research Organization:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24)
Contributing Organization:
The W7-X Team
Grant/Contract Number:
AC02-09CH11466; AC52-06NA25396
OSTI ID:
1353402
Alternate ID(s):
OSTI ID: 22738526
OSTI ID: 22925647
OSTI ID: 1407875
Report Number(s):
LA-UR--16-27305; PPPL--5316
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 4 Vol. 57; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

References (22)

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Service oriented architecture for scientific analysis at W7-X. An example of a field line tracer journal November 2013
Confirmation of the topology of the Wendelstein 7-X magnetic field to better than 1:100,000 journal November 2016
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Three-dimensional photogrammetric measurement of magnetic field lines in the WEGA stellarator journal December 2009
The limits and challenges of error field correction for ITER journal May 2012
Spectroscopic imaging of limiter heat and particle fluxes and the resulting impurity sources during Wendelstein 7-X startup plasmas journal August 2016
A high resolution IR/visible imaging system for the W7-X limiter journal August 2016
Overview of diagnostic performance and results for the first operation phase in Wendelstein 7-X (invited) journal October 2016
The spectral basis of optimal error field correction on DIII-D journal April 2014
Tracking of the magnet system geometry during Wendelstein 7-X construction to achieve the designed magnetic field journal May 2015
First measurements of error fields on W7-X using flux surface mapping journal August 2016
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Setup and initial results from the magnetic flux surface diagnostics at Wendelstein 7-X journal May 2016
Experimental and numerical study of error fields in the CNT stellarator journal May 2016
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The Trim Coils for the Wendelstein 7-X Magnet System journal June 2012
The Wendelstein 7-X Trim Coil System journal June 2014
The Superconducting Magnet System of the Stellarator Wendelstein 7-X journal March 2012
Analysis of the Magnetic Field Perturbations during the Assembly of Wendelstein 7-X journal September 2004
Flux Surface Mapping in LHD journal August 2010

Cited By (7)

Mapping of the HIDRA stellarator magnetic flux surfaces journal September 2019
Hessian matrix approach for determining error field sensitivity to coil deviations journal April 2018
Effect of toroidal plasma currents on the Wendelstein 7-X Scrape-Off Layer journal November 2019
Major results from the first plasma campaign of the Wendelstein 7-X stellarator journal July 2017
Measurements and correction of the 1/1 error field in Wendelstein 7-X journal December 2018
Methods for quantitative study of divertor heat loads on W7-X journal April 2019
Characterization of the W7-X scrape-off layer using reciprocating probes journal June 2019

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