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Irradiation Experiments and Thermal Analysis for Reactor System Design and Analysis at INL

Research output: Contribution to conferencePresentation

Abstract

Idaho National Laboratory (INL) is the nation's lead nuclear laboratory working to enhance reactor systems' safety, security, economics, and efficiency. Research and development (R&D) programs at INL support the current fleet of nuclear reactors for safer operation and newer reactors technology design, development, demonstration, and deployment. A major focus of INL's mission is the reactor system design and analysis supported by the irradiation experiments and thermal analysis of advanced and current-generation nuclear fuels and materials. The irradiation experiments and thermal analysis provide a deeper understanding of basic radiation damage processes that can determine the basis for performance improvements and verification of modeling assumptions. These experiments and analyses include experiment management: design, fabrication, characterization, irradiation, and post-irradiation examination. This research involves thermal, neutronic, and material investigation using the INL's Advanced Test Reactor (ATR) and Transient Reactor Test (TREAT) facilities. The results from these experiments and analysis are required to develop the regulatory basis for deploying new or modified fuels and materials. This seminar talk will also provide a general overview of the INL's research facilities, ongoing research programs, core capabilities, and opportunities for students and faculties.
Original languageEnglish
StatePublished - Feb 2022
EventMissouri University of Science and Technology - Missouri University of Science and Technology, Rolla, United States
Duration: Feb 14 2022Feb 14 2022

Conference

ConferenceMissouri University of Science and Technology
Country/TerritoryUnited States
CityRolla
Period02/14/2202/14/22

Keywords

  • Irradiation Experiments
  • Thermal Analysis
  • Reactor System
  • Design and Alanysis

INL Publication Number

  • INL/RPT-22-65890
  • 114669

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