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

被引：18
|
作者：
Tsige-Tamirat, H. [1 ]
Fischer, U. [1 ]
Serikov, A. [1 ]
Stickel, S. [1 ]
机构：
[1] Forschungszentrum Karlsruhe, Assoc FZK Euratom, Inst Reaktorsicherheit, D-76021 Karlsruhe, Germany
来源：
FUSION ENGINEERING AND DESIGN | 2008年 / 83卷 / 10-12期
关键词：
Monte Carlo; Geometry; CAD; MCNP; ITER;
D O I：
10.1016/j.fusengdes.2008.07.040
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The program McCad provides a CAD interface for the Monte Carlo transport code MCNP It is able to convert CAD data into MCNP input geometry description and provides GUI components for modeling, visualization, and data exchange. It performs sequences of tests on CAD data to check its validity and neutronics appropriateness including completion of the final MCNP model by void geometries. McCad has been used to convert a 40: ITER torus sector CAD model to a suitable MCNP geometry model. Results of MCNP calculations performed to validate the converted geometry are presented. (C) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码：1771 / 1773
页数：3
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