Fusion Science and Technology / Volume 64 / Number 3 / September 2013 / Pages 687-691
Test Blanket, Fuel Cycle, and Breeding / Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 / dx.doi.org/10.13182/FST13-A19172
In this work, a model has been developed to calculate the neutron wall loading poloidal distribution in a generic tokamak plasma and vessel geometry on the basis of Monte Carlo simulation. Different neutron source radial profiles corresponding to advanced plasma scenarios have been implemented in this model, using combinations of step and parabolic functions.
The model has been validated with data from state-of-the-art simulations of ITER wall loading, and a parametric study has been performed over different plasma geometries and radial profiles to check the variability of the neutron poloidal profile.
The results show the effect of the different configurations on neutron wall loading. This model can be used for parametric studies for conceptual design or systems analysis activities.