Abstract
Recent advances in radiation transport simulation tools enable an increased fidelity and accuracy in modeling complex geometries in fusion systems. Future neutronics calculations will increasingly be based directly on these 3-D CAD-based geometries, allowing enhanced model complexity and improved quality assurance. Improvements have been made in both stochastic and deterministic radiation transport methodologies and their new capabilities will be compared briefly. A code comparison benchmark exercise has been specified based on a 40° sector of the ITER machine and the analysis results show good agreement. Additional analyses will be discussed, with particular attention to how these new capabilities provide new insights for engineering design of ITER components.
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