Modeling of fuel retention in the pre-damaged tungsten with MeV W ions after exposure to D plasma

Abstract

Modeling of high-Z ion irradiated-induced damages on fuel retention inside tungsten (W) material has been performed in this work. The upgraded Hydrogen Isotope Inventory Processes Code (HIIPC) is applied to model the deuterium (D) retention inside pre-damaged W during exposed to low-energy D flux, and the W is pre-irradiated by 20 MeV W-ion before exposed to D flux. Three types of trap, i.e. mono-vacancies, dislocations and grain boundary vacancies, are considered in the present model. The mono-vacancy defects induced by energetic W ions are calculated by SRIM code. First, the model is validated against the available experimental data under the same D flux exposure conditions, showing the reasonable agreement. Then, the effect of radiation-induced defects produced by pre-exposed energetic W-ion with different energy and fluence on the fuel retention are studied, confirming that the irradiation-induced traps play a dominated role on the fuel retention in the surface of the material (∼ micrometer). Finally, the effects of different type of defect, D fluence, and wall temperature on the fuel retention are discussed systemically, and these modeling results are in well agreement with the previous studies.

Keywords

• Fuel retention
• Tungsten
• Irradiated-induced damage