Estimation of the tritium retention in ITER tungsten divertor target using macroscopic rate equations simulations - Archive ouverte HAL Access content directly
Conference Papers Year : 2017

Estimation of the tritium retention in ITER tungsten divertor target using macroscopic rate equations simulations

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Abstract

Based on macroscopic rate equation simulations of tritium migration in an actively cooled tungsten (W) plasma facing component (PFC) using the code MHIMS (migration of hydrogen isotopes in metals), an estimation has been made of the tritium retention in ITER W divertor target during a non-uniform exponential distribution of particle fluxes. Two grades of materials are considered to be exposed to tritium ions: an undamaged W and a damaged W exposed to fast fusion neutrons. Due to strong temperature gradient in the PFC, Soret effect's impacts on tritium retention is also evaluated for both cases. Thanks to the simulation, the evolutions of the tritium retention and the tritium migration depth are obtained as a function of the implanted flux and the number of cycles. From these evolutions, extrapolation laws are built to estimate the number of cycles needed for tritium to permeate from the implantation zone to the cooled surface and to quantify the corresponding retention of tritium throughout the W PFC.
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Dates and versions

hal-02737442 , version 1 (02-06-2020)

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Etienne Hodille, Elodie Bernard, S. Markelj, J. Mougenot, C. S. Becquart, et al.. Estimation of the tritium retention in ITER tungsten divertor target using macroscopic rate equations simulations. 16. International Conference on Plasma-Facing Materials and Components for Fusion Applications, May 2017, Bristol, Germany. ⟨hal-02737442⟩
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