Application of CAD-neutronics coupling to geometrically complex fusion systems

Author

Sawan, M.E. ; Wilson, P.P.H. ; Tautges, T. ; El-Guebaly, L.A. ; Henderson, D.L. ; Bohm, T.D. ; Marriott, E.P. ; Kiedrowski, B. ; Smith, B. ; Ibrahim, A. ; Slaybaugh, R.

Author_Institution

Fusion Technol. Inst., Univ. of Wisconsin-Madison, Madison, WI, USA

fYear

2009

fDate

1-5 June 2009

Firstpage

1

Lastpage

6

Abstract

An innovative computational tool (DAG-MCNP) has been developed for efficient and accurate 3-D nuclear analysis of geometrically complex fusion systems. Direct coupling with CAD models allows preserving the geometrical details, eliminating possible human error, and faster design iterations. DAG-MCNP has been applied to perform 3-D nuclear analysis for several fusion designs and demonstrated the ability to generate high-fidelity high-resolution results that significantly improve the design process. This tool will be the core for a full CAD-based simulation predictive capability that couples engineering analyses directly to the CAD solid model.

Keywords

CAD; Monte Carlo methods; Tokamak devices; fusion reactor blankets; fusion reactor design; fusion reactor divertors; neutron flux; neutron transport theory; nuclear engineering computing; 3-D nuclear analysis; CAD-neutronics coupling; DAG-MCNP; ITER components; Monte Carlo radiation transport; computational tool; divertor; fusion device designs; geometrically complex fusion systems; neutron flux; test blanket module; Acceleration; Design automation; Fusion power generation; Geometry; Humans; Monte Carlo methods; Process design; Ray tracing; Solid modeling; Testing; 3-D nuclear analysis; CAD models; Monte Carlo;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on

Conference_Location

San Diego, CA

Print_ISBN

978-1-4244-2635-5

Electronic_ISBN

978-1-4244-2636-2

Type

conf

DOI

10.1109/FUSION.2009.5226505

Filename

5226505