Title :
Neutronics Assessment of the ITER First Wall/Shield Modules
Author :
Sawan, M.E. ; Smith, B. ; Wilson, P.
Author_Institution :
Wisconsin Univ., Madison
Abstract :
Neutronics analysis was performed to support the US design of ITER first wall/shield (FWS) modules 7, 12 and 13. Initial 1-D and 2-D calculations determined nuclear heating radial profiles in each of the constituent materials. In addition, the nuclear parameters were determined at the inner surface of the vacuum vessel (VV). The impact of radiation streaming through zones with large water content, such as the water coolant manifolds and FW attachment legs, was evaluated. The peaking is largest for nuclear heating that is dominated by gamma heating. Monte Carlo calculations that are directly coupled to the CAD models were utilized to generate high fidelity, high-resolution results for nuclear heating, radiation damage, and helium production.
Keywords :
Monte Carlo methods; fusion reactor design; fusion reactor materials; nuclear engineering computing; plasma heating; plasma simulation; radiation effects; 1D calculations; 2D calculations; CAD models; FWS modules; ITER first wall-shield modules; Monte Carlo calculations; gamma heating; helium production; neutronics analysis; nuclear heating radial profiles; radiation damage; radiation streaming; water coolant; Composite materials; Computational fluid dynamics; Coolants; Heating; Helium; Neutrons; Performance analysis; Plasmas; Production; Steel; ITER; helium production; neutronics; nuclear heating; shield modules;
Conference_Titel :
Fusion Engineering, 2007. SOFE 2007. 2007 IEEE 22nd Symposium on
Conference_Location :
Albuquerque, NM
Print_ISBN :
978-1-4244-1193-1
Electronic_ISBN :
978-1-4244-1194-8
DOI :
10.1109/FUSION.2007.4337913
