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Safety Considerations for Advanced Material Irradiation at the ATR

  • Daniel Kelly Sluder
  • , Nate Oldham
  • , Jacob Lewis Westacott
  • , Duane Ball

Research output: Contribution to conferencePresentationpeer-review

Abstract

The Advanced Test Reactor (ATR) is a light water reactor with aluminum-clad driver fuel. A primary mission of the ATR is to support the next generation of nuclear reactors. This support necessarily requires irradiation of advanced materials such as sodium, fuel salts, and metal eutectics. Irradiation of advanced materials in the ATR environment presents a challenge when completing accident analyses and demonstrating compliance to the Safety Analysis Report (SAR). Many advanced materials have the possibility to react with the ATR protective barriers such as the cladding or primary coolant system (PCS) boundary during postulated accident scenarios. Further, molten fuel experiments fall outside of the standard regulatory framework for dose consequence analyses. ATR is currently developing new safety analysis methods to support irradiation of advanced materials. The primary considerations for this development are 1) experiment containment design requirements, 2) primary coolant system response to an experiment containment failure, and 3) dose analyses for molten fuels.
Original languageEnglish
StatePublished - 2024
Event2024 ANS Annual Conference on Advanced Reactor Safety, ARS 2024 - Las Vegas, United States
Duration: Jun 16 2024Jun 19 2024

Conference

Conference2024 ANS Annual Conference on Advanced Reactor Safety, ARS 2024
Country/TerritoryUnited States
CityLas Vegas
Period06/16/2406/19/24

Keywords

  • 21 - SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
  • 38 - RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
  • 11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS
  • Advanced Reactor Safety
  • Radiological Consequences
  • Irradiation Experiments
  • Material Interaction
  • Structural Analysis

INL Publication Number

  • INL/CON-24-77970
  • 175988

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