Title
  
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.

Upcoming Events

See Full Calendar

News Highlights

 

Type
  
Title
  
Name
  
Modified
  
Modified By
  
Abstract
Article
MoreLink
  
2023 ART GCR Meeting screenshot.PNG2023 DOE-NE ART GCR Annual Review
  
8/1/2023 9:53 AMamy.boll@inl.gov
July 25-27, 2023
Virtual Meeting
https://art.inl.gov/2023%20Meetings/Forms/AllItems.aspx?RootFolder=%2F2023%20Meetings%2F2023%20DOE%2DNE%20ART%20GCR%20Program%20Review&FolderCTID=0x01200039F72F60F8304049B055C9ACA1A7C119&View=%7B5C189A0B%2DCD13%2D4152%2DAB59%2D8526A7D0625D%7D
71441_Kernel Buffer.pngKernel Buffer Volume Fraction Margin of the AGR Designed Fuel Particle
  
8/1/2023 10:02 AMamy.boll@inl.gov
Modeling results used to assess the fuel performance of the TRISO-coated fuel particles as a function of kernel/buffer volume fraction.
Modeling results used to assess the fuel performance of the TRISO-coated fuel particles as a function of kernel/buffer volume fraction.
https://www.osti.gov/biblio/1962863
Advanced_GC.pngAdvanced Graphite Creep Uncertainty Analysis
  
2/25/2022 10:01 AMJodi L. Vollmer
Results from the Uncertainty Quotient Tool (UQTool) which has been developed to determine dose uncertainty for irradiated material tests within all Material Test Reactors.
Advanced Graphite Creep Uncertainty Analysis
https://art.inl.gov/Rotating%20Files/AGC.pdf
ORNL_TM-2021_2357.pngUpgrade of Gamma Spectrometry Systems for ORNL TRISO Fuel PIE
  
2/25/2022 9:21 AMJodi L. Vollmer
Upgrades to ORNL Gamma Spectrometry Systems Used for PIE of AGR Experiments.
Upgrades to ORNL Gamma Spectrometry Systems Used for PIE of AGR Experiments.
https://art.inl.gov/Rotating%20Files/ORNL_TM-2021_2357-R0.pdf
PARFUME_As_Run.pngAGR-5/6/7 Irradiation As Run Predictions Using PARFUME
  
2/22/2022 2:08 PMJodi L. Vollmer
The PARFUME, a fuel performance modeling code used for high-temperature gas-cooled reactors, was used to model the AGR-5/6/7 irradiation test using as-run physics and thermal data.
The PARticle FUel ModEl (PARFUME), a fuel performance modeling code used for high-temperature gas-cooled reactors, was used to model the Advanced Gas Reactor (AGR)-5/6/7 irradiation test using as-run physics and thermal data. This report documents the calculations performed to predict the failure probability of tristructural isotropic (TRISO)-coated fuel particles during the AGR-5/6/7 experiment.
https://art.inl.gov/Rotating%20Files/64576%20AGR-567_PARFUME_As_Run.pdf
Title
  
HighlightText
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.
To read full article  https://www.zmescience.com/other/feature-post/triso-particles-nuclear-04062020/
  
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) particle fuel has long been used in high-temperature gas-cooled nuclear reactors, but it is seeing a resurgence as a result of other applications. Read more
To read full article: https://www.powermag.com/the-allure-of-triso-nuclear-fuel-explained/
  
Idaho National Laboratory Fellow Emeritus David Petti has been named to the National Academy of Engineering for leadership in developing high-temperature nuclear reactor fuels and improving the safety of fission and fusion reactors
To read full article see - https://www.nae.edu/270224/National-Academy-of-Engineering-Elects-111-Members-and-22-International-Members

 

 

​Vulnerability Disclosure Proigram