References
- “MCNP—AGeneral Monte Carlo N-ParticleTransport Code, Version 5,” LA-UR-03-1987, Los Alamos National Laboratory (2003).
- H. TSIGE-TAMIRAT et al., “Automatic Generation of a JET 3D Neutronics Model from CAD Geometry Data for Monte Carlo Calculations,” Fusion Eng. Des., 75–79, 891 (2005).
- Y. WU et al., “Research and Development of the Automatic Modeling System for Monte Carlo Particle Transport Simulation,” Chin. J. Nucl. Sci. Eng., 26, 1, 20 (2006).
- M. WANG et al., “Three-Dimensional Modeling of Complex Fusion Devices Using CAD-MCNPX Interface,” Fusion Sci. Technol., 47, 1079 (2005).
- S. SATO, H. IIDA, and T. NISHITANI, “Development of CAD/MCNP Interface Program Prototype for Fusion Reactor Nuclear Analysis,” Fusion Eng. Des., 81, 2767 (2006).
- N. SHAABAN et al., “A New Developed Interface for CAD/MCNP Data Conversion,” Proc. 14th Int. Conf. Nuclear Engineering, Miami, Florida, July 17–20, 2006, American Society of Mechanical Engineering (2006).
- D. LOPEZ AL-DAMA and A. TRKOV, “FENDL-2.1, Update of an Evaluated Nuclear Data Library for Fusion Applications,” INDC(NDS)-467, International Atomic Energy Agency (2004).
- P. P. H. WILSON et al., “State-of-the-Art 3-D Radiation Transport Methods for Fusion Energy Systems,” Fusion Eng. Des., 83, 824 (2008).