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​​​This Library is the content area for the home page slider. To add a new slide, just drag and drop a properly sized image below and add the following information:

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AGR567.jpg Final AGR-5/6/7 Fuel Experiment
The Advanced Gas Reactor (AGR) 5/6/7 tristructural isotropic  fuels experiment test train, which represents the final set of AGR experiments at Idaho National Laboratory, began irradiation in the Advanced Test Reactor on February 16, 2018.
The Advanced Gas Reactor (AGR) 5/6/7 tristructural isotropic (TRISO) fuels experiment test train, which represents the final set of AGR experiments at Idaho National Laboratory (INL), began irradiation in the Advanced Test Reactor (ATR) on February 16, 2018. The AGR TRISO Fuels Program irradiation experiment series will provide important data to support fuel qualification and fuel performance margin tests, leading to subsequent licensing of fuel for high-temperature gas reactors
https://art.inl.gov/Rotating%20Files/AGR567_Test_Train.pdf
HTR History.JPG History of High Temperature Reactors
The idea of a nuclear reactor operating at high temperature was first conceived in the early days of nuclear power plant development.
The idea of a nuclear reactor operating at high temperature (>700C) was first conceived in the early days of nuclear power plant development and government programs were instituted to develop the fuels, materials, and power conversion systems that could withstand these temperatures.
https://art.inl.gov/Rotating%20Files/HTR_History.pdf
Spotlight'18.jpg Neutron Irradiation-Induced Damage & Associated Intragranular FPTM
Neutron Irradiation-Induced Damage and Associated Intragranular Fission Product Transport Mechanisms in SiC Layer of TRISO Fuel Particles.
Certain metallic fission products are found to transport into and through the SiC layer of TRISO nuclear fuel particles, and various studies have been undertaken to understand this transport behavior. While the trapping or precipitation of fission products in the form of multi phased complex compounds at grain boundaries is most probable from a metallurgical perspective.
https://art.inl.gov/Rotating%20Files/Spotlight%20TRISO/Spotlight'18_TRISO_June.pdf
TRISO_Particle.png Overview of HTR Technology Development and Deployment
Overview of High Temperature Reactor Technology Development and Deployment
Overview of High Temperature Reactor Technology Development and Deployment
https://art.inl.gov/Rotating%20Files/HTR_Development.pdf