Abstract
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.
Highlights
IntroductionThe Equatorial Visible/Infra-Red Wide Angle Viewing System (WAVS) [1] plays a key role in machine protection by providing on-line monitoring of the surface temperature of plasma facing components, in order to avoid excessive heating
One of the most critical issues for ITER neutronics analysis concerns the assessment of radiation levels behind the Equatorial Port Plugs
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
Summary
The Equatorial Visible/Infra-Red Wide Angle Viewing System (WAVS) [1] plays a key role in machine protection by providing on-line monitoring of the surface temperature of plasma facing components, in order to avoid excessive heating. In addition to support diagnostics, the Port Plugs shall provide sufficient radiation shielding to attenuate the propagation of the intense, high-energy plasma-neutron flux. The Port Plug itself in the Port and the diagnostics create feedthroughs and streaming gaps, allowing the neutron flux to penetrate deeply into the Port Plug structures. This neutron irradiation could lead to significant activation of structural materials, with subsequent decay gamma emissions, contributing to the shutdown dose rate
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