Skip to content
  • 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: Warns, Kyle

Prognostic model and failure mechanisms of steam generators in Sodium-Cooled fast reactors

This paper presents a prognostic model for sodium-cooled fast reactor (SFR) steam generators (SGs). The purpose of the model is to support the decision making of autonomous control systems based on the reaming useful life estimation. SFR SGs are of great interest for plant integrity due to their harsh operation environment. They operate at higher […]

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.

Contact