EPJ Web Conf.
Volume 153, 2017ICRS-13 & RPSD-2016, 13th International Conference on Radiation Shielding & 19th Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society - 2016
|Number of page(s)||7|
|Section||2. Shielding Experiments & Benchmarks|
|Published online||25 September 2017|
A Monte-Carlo Benchmark of TRIPOLI-4® and MCNP on ITER neutronics
1 CEA,DEN/DER, Cadarache, 13108 Saint-Paul-lez-Durance, France
2 CEA, IRFM, Cadarache, 13108 Saint-Paul-lez-Durance, France
3 CIEMAT, Avda.Complutense, 40, Madrid 28040, Spain
4 F4E, Josep Pla 2, Torres Diagonal Litoral B3, 08019 Barcelona, Spain
5 ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 Saint-Paul-lez-Durance, France
a Corresponding author: email@example.com
Published online: 25 September 2017
Radiation protection and shielding studies are often based on the extensive use of 3D Monte-Carlo neutron and photon transport simulations. ITER organization hence recommends the use of MCNP-5 code (version 1.60), in association with the FENDL-2.1 neutron cross section data library, specifically dedicated to fusion applications. The MCNP reference model of the ITER tokamak, the ‘C-lite’, is being continuously developed and improved. This article proposes to develop an alternative model, equivalent to the 'C-lite', but for the Monte-Carlo code TRIPOLI-4®. A benchmark study is defined to test this new model. Since one of the most critical areas for ITER neutronics analysis concerns the assessment of radiation levels and Shutdown Dose Rates (SDDR) behind the Equatorial Port Plugs (EPP), the benchmark is conducted to compare the neutron flux through the EPP. This problem is quite challenging with regard to the complex geometry and considering the important neutron flux attenuation ranging from 1014 down to 108 n•cm-2•s-1. Such code-to-code comparison provides independent validation of the Monte-Carlo simulations, improving the confidence in neutronic results.
© The Authors, published by EDP Sciences, 2017
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