IntroMessage
  
Advanced Reactor Technologies (ART)  is a national program funded by the U.S. Department of Energy (DOE). Here at INL, work is focused specifically on developing a High Temperature Gas-cooled Reactor (HTGR), which will offer enhancements in safety and efficiency. This HTGR has a modularized design, which enables plants with larger power demands to simply build more than one module.  Modularization requires no extra design work and increases safety and efficiency by allowing a singular module to run or be stopped at any given time in the event of an incident or a changing need for power. HTGRs also produce process heat during operation, making them ideal for location near other industrial plants that could put this process heat to use in their own production and thus reduce the need for non-renewable energy sources upon which these plants currently rely.

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Abstract
Article
  
HTM.JPGAlloy 617 Qualified For New Use
  
5/5/2020 6:53 AMJodi L. Vollmer
A team at INL in collaboration with groups at ANL and ORNL, as well as industry consultants and international partners, has for the first time in 30 years gotten a new material, Alloy 617, into the Code.
Commercial Alloy Qualified For New Use, Expanding Nuclear Operating Temperature
https://art.inl.gov/Rotating%20Files/Commercial_alloy_qualified%20_for_new_use.pdf
HTR History.JPGHistory of High Temperature Reactors
  
9/20/2019 10:14 AMnikki.peterson@inl.gov
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/Past%20Articles/HTR_History.pdf
Special_Award.pngFraming Safety Renewing Safety Standards
  
9/20/2019 1:03 PMnikki.peterson@inl.gov
Three INL researchers awarded by ANS for their enhancement of regulatory framework for advanced nuclear reactors.
Framing Safety Renewing Safety Standards
https://art.inl.gov/Rotating%20Files/ART_Receives_ANS_Special_Award.pdf
TEST EXT-19-53723_Strength After Oxidation.pngDegradation of Strength under Oxidizing Conditions
  
1/20/2020 2:53 PMJodi L. Vollmer
Degradation of Strength under Oxidizing Conditions
The Degradation of Strength under Varying Oxidizing Conditions for Nuclear Graphite, INL/EXT-19-53723, April 2019.
https://art.inl.gov/Rotating%20Files/EXT-19-53723_Strength%20After%20Oxidation_R0.pdf
  
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FullStory
  
TRi-structural ISOtropic particle fuel — or TRISO, for short — is a type of micro fuel particle, quite possibly the most robust type of nuclear fuel.
  
The basic idea behind all nuclear power plants is the same: Convert the heat created by nuclear fission into electricity. There are several ways to do this, but in each case it involves a delicate balancing act between safety and efficiency. A nuclear reactor works best when the core is really hot, but if it gets too hot it will cause a meltdown and the environment will get poisoned and people may die and it will take billions of dollars to clean up the mess.
  
Tristructural isotropic (TRISO) coated particle fuel is a robust, microencapsulated fuel form developed originally for use in
high-temperature gas-cooled reactors (HTGRs).
To read full article see Nuclear News August 2020, Vlume 63, Number 9 https://www.ans.org/pubs/magazines/nn/
  
Tristructural isotropic (TRISO) coated particle fuel is a robust, microencapsulated fuel form developed originally for use in
high-temperature gas-cooled reactors (HTGRs).
To read full article see Nuclear News August 2020, Vlume 63, Number 9 https://www.ans.org/pubs/magazines/nn/

 

 

Labor Day56924Sept 7True6/23/2020 3:50:18 PM6https://art.inl.gov/Lists/Calendar/calendar.aspxFalse
GAIN-EPRI-NEI Sensor Technologies for Advanced Reactors Workshop56925Sept 22True https//gain.inl.gov/SitePages/SensorTechnologiesWorkshop.aspx 6/22/2020 5:14:03 PM7https://art.inl.gov/Lists/Calendar/calendar.aspxFalse