Nuclear

  • High Temperature Molten Salts Chemistry and Electrochemistry

    Zhao- University of Idaho

    Research Overview

    High temperature molten salt systems find extensive application in energy storage and conversion, materials processing, and reprocessing. Molten salt reactors (MSRs) were developed at Oak Ridge National Laboratory in the 1950s–1970s as one of the advanced high temperature nuclear reactor systems offering a potentially safer, more efficient and sustainable form of nuclear power.

    The eutectic alkaline metal fluoride salt mixture LiF-NaF-KF is identified as a promising candidate for molten salt reactors. The corrosion rate and mechanism are key to understanding, selecting, and designing new metal alloys for MSRs. Developing Ni-ODS (oxide dispersion strengthened) alloys can alleviate problems related to swelling and irradiation damage.

    Student Research Experience

    CAES provides a collaborative research environment with a strong safety culture that will nurture undergraduate students for strong leadership in research. Students will be trained following safety procedures and learn how to use a glovebox and handle hot molten salt safely. They will learn how to prepare samples and characterize corrosions.

    Students will learn how to record experimental work and report results professionally and effectively. This project provides a window for REU students to examine molten salt reactors and energy storage systems. Students are expected to review and learn the Working Control Document (WCD) as part of the lab’s rigorous safety culture.

    Skills & Techniques

  • Effect of Pressure Resistance Welded Molybdenum Alloy’s Response to Helium Ion Irradiation

    Charit – University of Idaho

    Research Overview

    The overarching goal is to explore and understand the irradiation response of pressure resistance welding (PRW) technology on two molybdenum-based materials: commercially pure molybdenum and an oxide (La₂O₃) dispersion strengthened molybdenum alloy, MoLa. The project aims to understand the effect of helium ion irradiation on the microstructural, microchemical and mechanical properties of these materials.

    There has been significant interest in the potential use of molybdenum-based materials among high melting refractory metals/alloys to produce fuel elements for the nuclear thermal rocket engine as well as accident-tolerant fuel cladding applications in advanced light water reactors. The benefits of molybdenum include its high melting point, high thermal conductivity, elevated temperature mechanical properties, and excellent corrosion resistance against liquid metals and aggressive environments.

    Student Research Experience

    The student will have the unique opportunity to learn about the potential use of refractory metals in terrestrial and extra-terrestrial nuclear reactors, and will participate in hands-on characterization of ion irradiated samples and data analysis. They will gain hands-on experience in scanning electron microscopy, energy dispersive spectroscopy and nanoindentation during the project period.

    They will also have the opportunity to observe operation of a high resolution transmission electron microscope by an instrument scientist. Near the end of the project, the student will present findings in microstructure-properties correlations via a presentation.

    Skills & Techniques