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Progress of conversion system from CAD data to MCNP geometry data in Japan

  • Published:2010-12 Issue:7-9 Volume:85 Page:1546-1550
  • ISSN:0920-3796
  • Container-title:Fusion Engineering and Design
  • language:en
  • Short-container-title:Fusion Engineering and Design

Author:

Sato S.,Nashif H.,Masuda F.,Morota H.,Iida H.,Konno C.

Publisher

Elsevier BV

Subject

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

Reference7 articles.

1. MCNP—A General Monte Carlo N-particle Transport Code, Version 5, LA-UR-03-1987;X-5 Monte Carlo Team,2003

2. Automatic generation and validation of an ITER neutronics model from CAD data;Tsige-Tamirat;Fusion Engineering and Design,2007

3. CAD-based interface programs for fusion neutron transport simulation;Wu;Fusion Engineering and Design,2009

4. State-of-the-art 3-D radiation transport methods for fusion energy systems;Wilson;Fusion Engineering and Design,2008

5. Development of CAD-TO-MCNP model conversion system and its application to ITER;Sato;Nuclear Technology,2009

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1. Study on Unstructured Mesh–Based Monte Carlo/Deterministic Coupled Particle Transport Calculation Method;Nuclear Science and Engineering;2024-02-09

2. Development of the automatic void generation module in GEOUNED conversion tool;Fusion Engineering and Design;2021-07

3. Development of cosVMPT and Application of Creating 3D Neutronics Model for 360-Degree CFETR;Journal of Fusion Energy;2021-03-26

4. CMGC: a CAD to Monte Carlo geometry conversion code;Nuclear Science and Techniques;2020-08

5. FluDAG: A CAD based tool for high energy physics;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2019-01
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