Acceleration techniques for the direct use of CAD-based geometry in fusion neutronics analysis

MCNP-A general Monte Carlo code for neutron and photon transport

J.F. Briesmeister · CERN Document Server (European Organization for Nuclear Research) · 1986 · 710 citations

Engineering, Nuclear Engineering, Physics +14

Benchmarking of MCAM 4.0 with the ITER 3D model

Yanfen Li, Lei Lu, A. Adam Ding et al. · Fusion Engineering and Design · 2007 · 85 citations

Computing, Computational Engineering, Computer Science +8

CGM: A Geometry Interface for Mesh Generation, Analysis and Other Applications

T. Tautges · Engineering With Computers · 2001 · 45 citations

Computing, Computational Engineering, Computer Science +16

Acceleration techniques for direct use of CAD-based geometries in Monte Carlo radiation transport

Timothy J. Tautges, Paul Wilson, Jason A. Kraftcheck et al. · 2009 · 34 citations

Architecture, Computer Engineering, Computer Science +15

Use of McCad for the conversion of ITER CAD data to MCNP geometry

H. Tsige-Tamirat, U. Fischer, A. Serikov et al. · Fusion Engineering and Design · 2008 · 26 citations

Architecture, Computer Science, Computational Geometry +3