Automatic generation and validation of an ITER neutronics model from CAD data-Reference-Cited by-同舟云学术

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Automatic generation and validation of an ITER neutronics model from CAD data

Published:2007-10 Issue:15-24 Volume:82 Page:1956-1959
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Tsige-Tamirat H.,Fischer U.,Serikov A.,Stickel S.

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference2 articles.

1. H. Tsige-Tamirat, U. Fischer, CAD Interface for Monte Carlo Particle Transport Codes, The Monte Carlo Method, Chattanooga, Tennessee, April 17–21, 2005 (ANS).

2. J.F. Briesmeister (ed.), MCNP—A General Monte Carlo N-Particle Transport Code, Version 4C, LANL, Report LA-13709-M, 2000.

Cited by 5 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. The McCad Code for the Automatic Generation of MCNP 3-D Models: Applications in Fusion Neutronics;IEEE Transactions on Plasma Science;2014-04

2. Nuclear Analysis of an ITER Blanket Module;Journal of Fusion Energy;2013-08-02

3. Study on three-dimensional heterogeneous calculation of ITER test blanket module with deterministic method;Fusion Engineering and Design;2013-06

4. Progress of conversion system from CAD data to MCNP geometry data in Japan;Fusion Engineering and Design;2010-12

5. Neutronic Modeling Challenges for the ITER ECRH Launcher Shielding Design;Nuclear Technology;2009-11

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