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  • Program Areas
    • TRISO Fuel Qualification
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  • 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: Nhat Nguyen, Khang H.

PRLO Code Interface & Workflow – 2025 Advances in Nuclear Fuel Management (ANFM) Workshop

This is a workshop presentation material, introducing the Plant ReLoad Optimization (PRLO) Interface and workflow.

Surrogate Modeling – 2025 Advances in Nuclear Fuel Management (ANFM) Workshop

This is a workshop presentation material, introducing surrogate modelling.

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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