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
Link To Document :
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