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  • Program Areas
    • TRISO Fuel Qualification
    • Graphite Qualification
    • High-Temperature Metals
    • Design, Methods, and Validation
  • NDMAS
  • Contacts
    • TRISO Fuel Qualification
    • Graphite Qualification
    • Design, Methods and Validation
    • High Temperature Metals
  • Program Areas
    • TRISO Fuel Qualification
    • Graphite Qualification
    • High-Temperature Metals
    • Design, Methods, and Validation
  • NDMAS
  • Contacts
    • TRISO Fuel Qualification
    • Graphite Qualification
    • Design, Methods and Validation
    • High Temperature Metals
  • Program Areas
    • TRISO Fuel Qualification
    • Graphite Qualification
    • High-Temperature Metals
    • Design, Methods, and Validation
  • NDMAS
  • Contacts
    • TRISO Fuel Qualification
    • Graphite Qualification
    • Design, Methods and Validation
    • High Temperature Metals
  • Program Areas
    • TRISO Fuel Qualification
    • Graphite Qualification
    • High-Temperature Metals
    • Design, Methods, and Validation
  • NDMAS
  • Contacts
    • TRISO Fuel Qualification
    • Graphite Qualification
    • Design, Methods and Validation
    • High Temperature Metals

author: Yang, Yong

Advanced Electron Microscopy of TRISO coated Particles: FY2021 Overview

Objectives: Understanding Effects of Irradiation on TRISO layers Fission product chemistry and behavior in UCO kernel Identify and Understand Fission Product Transport Mechanisms in TRISO Coated Particles

The DOE Office of Nuclear Energy Advanced Reactor Technologies (ART) Gas-Cooled Reactor (GCR) program supports research to reduce technical risk and enable deployment of advanced gas-cooled reactors.

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