Channeling Mode Ion Beam Analysis of Deuterium Retention in Damaged Tungsten for Fusion Research (IBADeTung)

Type of project: national project

Duration: 2025 - 2027

Project leader: Dr Esther Punzón QuijornaCode: J2-60052Coworkers: Dr Mitja Kelemen, Doc. Dr Sabina Markelj, Dr Primož Vavpetič, Dr Andreja Šestan ZavašnikExternal coworkers: Dr Janez ZavašnikPartners: Jožef Stefan Institute

In a world that increasingly demands more energy, controlled nuclear fusion offers a promising path to sustainable energy by replicating the sun’s power generation process. Fusion reactions involving hydrogen isotopes (HI), deuterium (D), and tritium (T) are the leading approach for future reactors. Tungsten (W), due to its low HI retention, low sputtering yield and good thermal conductivity, is the primary candidate for plasma-facing materials. However, neutron irradiation in D-T fusion damages tungsten’s crystal lattice, altering HI retention and transport.

This research addresses a key gap in understanding how lattice damage impact HI retention. The project employs Rutherford Backscattering Spectrometry (RBS) and Nuclear Reaction Analysis (NRA) in channeling configurations (RBS-C, NRA-C) to study defect structures, damage evolution, and HI retention. RBS-C assesses lattice damage, while NRA-C, using the ³He reaction with deuterium, quantifies trapped deuterium and determines its precise lattice location. Complementary techniques such as Transmission Electron Microscopy (TEM) and computational modelling will refine our understanding of damage’s role in hydrogen trapping.

Building on prior research, particularly the DeHydroC project, where RBS-C and NRA-C were used to study damage and HI retention under low damage doses and temperatures; this research extends the scope to extreme conditions. It addresses the lack of facilities replicating fusion reactor conditions with high particle fluxes and the presence of HI at elevated temperatures.

The stepwise approach includes defect structure differentiation using RBS-C, correlation with standard techniques such as TEM, and performing quantitative NRA for absolute deuterium amounts in individual defects. This innovative methodology, integrating experimental and theoretical approaches, aims to advance our understanding of defect analysis and HI retention in materials, contributing to the development of fusion energy. By combining experimental and computational methods, this project will provide critical insights into fusion reactor materials, supporting the development of radiation-resistant materials and aligning with broader efforts toward clean, sustainable energy solutions.

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