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: Unruh, Troy

Structural Materials Characterization Test Rig Development

Structural Materials Characterization Test Rig Development Project Summary

Real Time In-Core Instrumentation: From Fuel and Materials Irradiation tests to Advanced Reactor Demonstration -Flux Sensors

Real Time In-Core Instrumentation: From Fuel and Materials Irradiation tests to Advanced Reactor Demonstration -Flux Sensors Project Summary

A Two-Cycle Automated Approach to Electrical Resistivity Measurement of SiC Monitors for Peak Irradiation Temperature

An experimental system was designed and optimized to acquire real-time electrical resistance of the monitors during annealing. The system was then used to anneal irradiated silicon carbide (SiC) monitors. The altered resistance of the SiC monitors between the first heating cycle and the mean of the heating and cooling cycles that followed was found to […]

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