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    • Design, Methods and Validation
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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

author: Plummer, Mitchell A.

ECAR 1253 Results Of Reactor Physics Safety Analysis For Advanced Test Reactor (ATR) Cycle 148B

see ECAR

ECAR-1524 Results Of Reactor Physics Safety Analysis For Advanced Test Reactor (ATR) Cycle 149B

see ECAR

ECAR-1804 Results Of Reactor Physics Safety Analysis For Advanced Test Reactor (ATR) Cycle 151B

see ECAR

ECAR-1032 Results Of Reactor Physics Safety Analysis For Advanced Test Reactor (ATR) Cycle 147A

see ECAR 1032

ECAR-1804 Results Of Reactor Physics Safety Analysis For Advanced Test Reactor (ATR) Cycle 151B

see ECAR

ECAR-1742 Results Of Reactor Physics Safety Analysis For Advanced Test Reactor Cycle 151A

see ECAR

ECAR 1253 Results Of Reactor Physics Safety Analysis For Advanced Test Reactor (ATR) Cycle 148B

see ECAR

ECAR-1608 Results Of Reactor Physics Safety Analysis For Advanced Test Reactor (ATR) Cycle 150A

see ECAR

ECAR-1742 Results Of Reactor Physics Safety Analysis For Advanced Test Reactor Cycle 151A

see ECAR

ECAR-1032 Results Of Reactor Physics Safety Analysis For Advanced Test Reactor (ATR) Cycle 147A

see ECAR 1032

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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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