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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

author: Sackett, John

ARC-100 Transient Overpower Scenario Modeling

This report captures the analysis performed for the transient overpower scenario modeling for the ARC-100 reactor.

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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