NSUF 26-5622: Post-Irradiation Examination of MITR-Irradiated Advanced Moderator Module (AMM) Capsules: Multilayer Barrier Integrity, Hydrogen Retention, and Microstructural Evolution

This project will perform post-irradiation examination (PIE) of a MITR-irradiated Advanced Moderator Module (AMM) developed under the DOE-NE Microreactor Program to validate hermetic containment of yttrium hydride (YH₂−x) for high-temperature neutron moderation. The primary objectives are to (i) assess overall AMM containment integrity after irradiation, (ii) recover the irradiated YH₂−x pellet by controlled disassembly and independently characterize the H₂ permeation-barrier coating/Nb liner, Nb weld seals, and outer SiC composite shell, (iii) quantify irradiation-driven microstructural and chemical evolution at critical interfaces that could enable hydrogen loss or degradation, and (iv) measure irradiation-induced changes in thermal transport behavior of the coating/liner system.

Methods will include shielded sample preparation (sectioning/opening and cross-section preparation), SEM (imaging, EDS mapping, EBSD where applicable) for microstructural screening, site-specific FIB liftouts from coating/Nb/SiC/weld regions, high-resolution TEM/STEM with EDS/EELS for nanoscale defect and interfacial reaction-layer characterization, powder XRD of the recovered pellet to assess hydride phase stability and stoichiometry trends, and thermophysical measurements via laser flash analysis (and/or thermal conductivity microscopy depending on specimen geometry).

If successful, the work will provide the first direct irradiation-performance dataset linking hydrogen retention, barrier-coating integrity, and interfacial stability in an integrated microreactor moderator containment architecture (YH₂−x/Nb + barrier/SiC). This will significantly advance the state-of-the-knowledge by identifying irradiation-induced degradation modes (e.g., cracking, delamination, diffusion-assisted reaction layers, hydride phase changes) and establishing microstructural acceptance criteria for long-duration operations.

The anticipated scientific outcomes include quantitative evidence of hydride phase stability, nanoscale characterization of coating and weld performance under irradiation, and validated thermal-transport property changes, together enabling informed design optimization and down-selection of moderator containment strategies for deployable high-temperature microreactors.

Additional Info

Field Value
Awarded Institution Argonne National Laboratory
DOI 10.46936/NSUF/60017670
Embargo End Date 2028-04-22
Facility Tech Lead Noé Morales
NSUF Call FY 2026 RTE 1st Call
PI Sumit Bhattacharya
PIE Facilities Irradiated Materials Characterization Laboratory
Prep Facilities Irradiated Materials Characterization Laboratory
Project Member Dr. Yinbin Miao, Principal Materials Scientist - Argonne National Laboratory (https://orcid.org/0000-0002-3128-4275)
Project Member Dr. Sumit Bhattacharya, Principle Material Scientist - Argonne National Laboratory (https://orcid.org/0000-0002-6251-6075)
Project Type RTE