Status of the McCad geometry conversion tool and related visualization capabilities for 3D fusion neutronics calculations

被引：36

作者：

Grosse, D. ^{[1
]}

Fischer, U. ^{[1
]}

Kondo, K. ^{[1
]}

Leichtle, D. ^{[1
]}

Pereslavtsev, P. ^{[1
]}

Serikov, A. ^{[1
]}

机构：

[1] Karlsruhe Inst Technol, Assoc KIT Euratom, D-76344 Eggenstein Leopoldshafen, Germany

来源：

FUSION ENGINEERING AND DESIGN | 2013年 / 88卷 / 9-10期

关键词：

CAD; Monte Carlo; Neutronics; ITER; IFMIF; CAD-BASED GEOMETRY;

D O I：

10.1016/j.fusengdes.2013.02.146

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 McCad geometry conversion tool has been developed at KIT to enable the automatic conversion of CAD models into the semi-algebraic geometry representation as utilized in Monte Carlo particle transport simulations. McCad is entirely based on open source software, it is running under the Linux operating system and utilizes the Open Cascade CAD kernel with the Qt4 libraries for the graphical user interface (GUI). The converted geometry models can be output in the syntax of the Monte Carlo codes MCNP and TRIPOLI. Related visualization capabilities are based on the coupling of McCad with the ParaView software and allow to overlay mesh tally distributions to the CAD geometry. This enables perspective 3D representations or animations on the CAD geometry. The paper presents the current status of the McCad approach and its implementation, and discusses its capabilities, limitations as well as future development needs. The use of McCad for fusion neutronics applications is illustrated on the examples of the MCNP model generation for ITER Test Blanket Modules (TBM) and the test cell facility of the IFMIF neutron source including Monte Carlo shielding calculations using the converted models. (C) 2013 Elsevier B.V. All rights reserved.

引用

页码：2210 / 2214

页数：5

共 13 条

[1] Present status of the conceptual design of the EU test blanket systems [J].

Boccaccini, L. V. ;

Aiello, A. ;

Bede, O. ;

Cismondi, F. ;

Kosek, L. ;

Ilkei, T. ;

Salavye, J-F ;

Sardain, P. ;

Sedano, L. .

FUSION ENGINEERING AND DESIGN, 2011, 86 (6-8) :478-483

[2] Integral approach for neutronics analyses of the European test blanket modules in ITER [J].

Fischer, U. ;

Grosse, D. ;

Moro, F. ;

Pereslavtsev, P. ;

Petrizzi, L. ;

Villari, R. ;

Weber, V. .

FUSION ENGINEERING AND DESIGN, 2011, 86 (9-11) :2176-2179

[3] USE OF CAD GENERATED GEOMETRY DATA IN MONTE CARLO TRANSPORT CALCULATIONS FOR ITER [J].

Fischer, U. ;

Iida, H. ;

Li, Y. ;

Loughlin, M. ;

Sato, S. ;

Serikov, A. ;

Tsige-Tamirat, H. ;

Tautges, T. ;

Wilson, P. P. ;

Wu, Y. .

FUSION SCIENCE AND TECHNOLOGY, 2009, 56 (02) :702-709

[4]

Grosse D., 2009, C P P 2009 INT C MAT, pp JRC54365

[5] Neutronic analysis for the IFMIF target and test cell using a new CAD-based geometry model [J].

Kondo, Keitaro ;

Arbeiter, Frederik ;

Fischer, Ulrich ;

Grosse, Dennis ;

Heinzel, Volker ;

Klix, Axel ;

Serikov, Arkady ;

Tian, Kuo ;

Weber, Viktoria .

FUSION ENGINEERING AND DESIGN, 2012, 87 (7-8) :983-988

[6] Development of Monte Carlo automatic modeling functions of MCAM for TRIPOLI-ITER application [J].

Lu, L. ;

Lee, Y. K. ;

Zhang, J. J. ;

Li, Y. ;

Zeng, Q. ;

Wu, Y. C. .

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2009, 605 (03) :384-387

[7]

Matsumuto H., 2012, 20 TOP M TECHN FUS E

[8]

Okumura Y., 2012, 20 TOP M TECHN FUS E

[9] Shutdown dose rate analysis for the European TBM system in ITER [J].

Pereslavtsev, P. ;

Fischer, U. ;

Grosse, D. ;

Leichtle, D. ;

Majerle, M. .

FUSION ENGINEERING AND DESIGN, 2012, 87 (5-6) :493-497

[10] STATUS OF THE McDeLicious APPROACH FOR THE D-Li NEUTRON SOURCE TERM MODELING IN IFMIF NEUTRONICS CALCULATIONS [J].

Simakov, S. P. ;

Fischer, U. ;

Kondo, K. ;

Pereslavtsev, P. .

FUSION SCIENCE AND TECHNOLOGY, 2012, 62 (01) :233-239

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