Abstract
There is increasing demand for fast and accurate neutronics analysis to be conducted on specific ITER components. The ATLAS (accelerated torus-like angular source) algorithm has been developed to accelerate such neutronics calculations by approximating the 3-D plasma volume source as a surface source at the first-wall region of interest. The ATLAS routine rapidly calculates the angular distribution of the unscattered neutron flux at the chosen first wall location, on a discrete angular grid, and writes a surface source for both MCNP and Attila. This discretised source can then be used to accurately reproduce the full 3-D toroidal volume source in angle and energy, and to quickly simulate the irradiation of individual components or regions in the ITER model. While designed for ITER, the method is general in implementation and can be applied to any tokamak.
Original language | English |
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Pages (from-to) | 1825-1829 |
Number of pages | 5 |
Journal | Fusion Engineering and Design |
Volume | 86 |
Issue number | 9-11 |
DOIs | |
State | Published - Oct 2011 |
Externally published | Yes |
Funding
This work was funded by ITER and F4E through DWO-73-301-MJL-EU and F4E-2008-OPE-02-03. The views and opinions herein do not necessarily reflect those of the ITER organisation.
Keywords
- Attila
- ITER
- MCNP
- Neutron source
- Neutronics