Driven reconnection in magnetic fusion experiments
Error fields (i.e. small non-axisymmetric perturbations of the magnetic field due to coil misalignments, etc.) are a fact of life in magnetic fusion experiments. What effects do error fields have on plasma confinement? How can any detrimental effects be alleviated? These, and other, questions are explored in detail in this lecture using simple resistive magnetohydrodynamic (resistance MHD) arguments. Although the lecture concentrates on one particular type of magnetic fusion device, namely, the tokamak, the analysis is fairly general and could also be used to examine the effects of error fields on other types of device (e.g. Reversed Field Pinches, Stellerators, etc.).
- Research Organization:
- Univ. of Texas, Austin, TX (United States). Institute for Fusion Studies
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- FG05-80ET53088
- OSTI ID:
- 171359
- Report Number(s):
- DOE/ET/53088-730; IFSR-730; ON: DE96003966; TRN: 96:003717
- Resource Relation:
- Other Information: PBD: Nov 1995
- Country of Publication:
- United States
- Language:
- English
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