Title of article
TRIPOLI-4® Monte Carlo code ITER A-lite neutronic model validation
Author/Authors
Jaboulay، نويسنده , , Jean-Charles and Cayla، نويسنده , , Pierre-Yves and Fausser، نويسنده , , Clement and Damian، نويسنده , , Frédéric and Lee، نويسنده , , Yi-Kang and Puma، نويسنده , , Antonella Li and Trama، نويسنده , , Jean-Christophe، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2014
Pages
5
From page
2174
To page
2178
Abstract
3D Monte Carlo transport codes are extensively used in neutronic analysis, especially in radiation protection and shielding analyses for fission and fusion reactors. TRIPOLI-4® is a Monte Carlo code developed by CEA. The aim of this paper is to show its capability to model a large-scale fusion reactor with complex neutron source and geometry. A benchmark between MCNP5 and TRIPOLI-4®, on the ITER A-lite model was carried out; neutron flux, nuclear heating in the blankets and tritium production rate in the European TBMs were evaluated and compared. The methodology to build the TRIPOLI-4® A-lite model is based on MCAM and the MCNP A-lite model. Simplified TBMs, from KIT, were integrated in the equatorial-port. A good agreement between MCNP and TRIPOLI-4® is shown; discrepancies are mainly included in the statistical error.
Keywords
neutronics , Monte Carlo , Numerical benchmark , ITER A-lite , TRIPOLI-4®
Journal title
Fusion Engineering and Design
Serial Year
2014
Journal title
Fusion Engineering and Design
Record number
2362929
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