Nuclear Analysis of Toroidal and Poloidal Legs of ITER ELM Coils
Fusion Science and Technology / Volume 60 / Number 1 / July 2011 / Pages 113-117
ITER Systems / Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) / dx.doi.org/10.13182/FST11-A12336
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The ELM coils in ITER are used to provide control of Edge localized Modes (ELMs). These coils are located on the outboard side of ITER between the shield modules and vacuum vessel (VV) and are subject to high radiation levels. Detailed three-dimensional (3-D) models of the toroidal and poloidal legs of the ELM coils and manifolds, as well as homogenized first wall, shield, and VV components were created for the MCNP code. Neutronics calculations were performed to determine a variety of radiation damage parameters for the ELM coils as well as the VV located behind them. The results presented here include fast neutron fluence, insulator dose rate, He production, Cu dpa, and nuclear heating. VV heating and dpa are also presented. These results are being used to guide the evolving design of the ELM coils including thermal stress and thermal hydraulic analyses.
