Neutral Particle and Erosion/Redeposition Modeling of the FIRE Tokamak
Abstract
A detailed neutral analysis has been done on the Fusion Ignition Research Experiment (FIRE) tokamak. Inputs are ion/electron density, ion temperature, electron temperature, plasma flow velocities, and the geometry, which are all taken from the output of the UEDGE plasma transport code. The Monte Carlo neutral code DEGAS2 is then used to simulate the transport of neutral atoms and molecules to ultimately calculate the neutral flux, energy distribution, and power density deposited to the walls of the reactor. The simulation includes atomic charge exchange, ionization, and recombination as well as molecular dissociation, ionization, dissociative ionization, and dissociative recombination. The analysis has been done most recently for the detached plasma regime and previously for an attached plasma. In the new detached regime the edge temperature is roughly 1 eV, densities are around 3x10^21 m-3, and the ion flux is 1x10^22 m^2 s-1 at the outer divertor plate. The neutral flux and energy distribution from DEGAS2 are used in the REDEP code for erosion/redeposition analysis. Additionally, sputtering of beryllium from the first wall and subsequent deposition on divertor plates is considered. The effects of the mixed Be/W divertor surface on erosion/redeposition behavior are discussed.
- Publication:
-
APS Division of Plasma Physics Meeting Abstracts
- Pub Date:
- October 2000
- Bibcode:
- 2000APS..DPPUP1070A