Synergistic Irradiation, Corrosion, and Microstructural Evolution in Nuclear Materials: Poster Session
Sponsored by: TMS Structural Materials Division, TMS: Nuclear Materials Committee
Program Organizers: Djamel Kaoumi, North Carolina State University; Michael Short, Massachusetts Institute of Technology; Peter Hosemann, University of California, Berkeley; Stephen Raiman, University of Michigan; Raluca Scarlat, University of California, Berkeley; Aaron Kohnert, Los Alamos National Laboratory; Ryan Schoell, Sandia National Laboratory; Philip Edmondson, The University of Manchester; Celine Cabet, Commissariat a l'Energie Atomique

Tuesday 5:30 PM
March 1, 2022
Room: Exhibit Hall C
Location: Anaheim Convention Center

N-25: HIPE: A Versatile Test Platform for Hydrogen Permeability Measurements: Reid Bohanon1; Diego Macias1; Tu Le1; Stephen Raiman1; 1Texas A&M University
    Radiation enhanced diffusion (RED) is a major component of irradiation affected corrosion (IAC). To predict the behavior of corroding materials in an irradiated environment, there is a desire to better quantify microstructural effects on solid state diffusion with an externally applied chemical potential. For this work, materials were fabricated and processed to achieve specific microstructures. The materials were irradiated with a proton beam to test the influence of microstructural features on near-surface radiation effects. Coatings and diffusion bonding were used to tailor interfaces for studying diffusion across phase boundaries. This work reports early results from experiments designed to better understand how microstructure influences near-surface defect motion.

N-38: Development of Coatings to Provide Corrosion Resistance and Tritium Retention for Application in Nuclear Fusion Reactors: Hazel Gardner1; Alice Laferrere1; Callum Gallagher1; David Bowden1; 1The UK Atomic Energy Authority
    Nuclear fusion can supply abundant, low carbon energy with minimal long-term radioactive waste, making it a safe and sustainable future energy option. In a fusion powerplant, one way to prevent tritium fuel from diffusing throughout the structure is to coat structural materials with a tritium permeation barrier. These coatings must also provide corrosion resistance against coolants and be resistant to irradiation damage. This work outlines a materials development strategy for multifunctional coatings for fusion applications. Ceramic oxide and nitride coatings on Grade 91 steel substrates have been tested for thermal stability. Coating adhesion has been investigated through mechanical testing and microstructural characterisation of the coating-substrate interface. Ion irradiation studies demonstrate coating response to irradiation damage and retention of hydrogen isotopes is compared between different coating systems. Workflow for future corrosion testing in liquid metals and molten salts is presented alongside capabilities for developing multi-layer coatings tailored to different corrosive environments.