An Algorithm of Converting UG Model to MCNP Geometry Model

Author:

Zhang Jian Sheng1,Zhan Xi1

Affiliation:

1. Southwest University of Science and Technology

Abstract

MCNP input file has the characteristics of complicated form and is error-prone in describing geometry model. An algorithm of converting UG model to MCNP geometry model was researched and implemented through UG OPEN API and C++ programming language. The algorithm improves the efficiency of describing MCNP geometry model, and provides a valuable reference to MCNP users.

Publisher

Trans Tech Publications, Ltd.

Subject

General Engineering

Reference18 articles.

1. WU Yi-can, LI Ying, LU Lei, ed., 2006. Research and development of the automatic modeling system for Monte Carlo particle transport simulation. Chinese Journal of Nuclear Science and Engineering, 26(1): 20-27 (In Chinese).

2. DING Ai-ping, LI Ying, LU Lei, ed., 2006. Visualizing Input Files of Neutronics Model for MCNP Calculation. Nuclear Physics Review, 23(2): 130-133 (In Chinese).

3. FAN Jia-jin, WANG Yi, CHENG Jian-ping, ed., 2002. Development of visual platform of MCNP4B. Nuclear Electronics & Detection Technology, 22(1): 52-55 (In Chinese).

4. Tautges T. Wnag M., 2004. CAD-Based Monte Carlo Transport Using MCNPX and CGM. Transactions of the American Nuclear Society, 91: 185-6.

5. N. Borglund, J. Eriksson, E. Fumero, ed., 2004. Geometry package for Monte Carlo simulations on CAD files. Nuclear Instruments and Methods in Physics Research A, 525: 417-420.

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