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
  
2024 DOE NE ART GCR SNIP.png2024 ART GCR Annual Review - SAVE THE DATE
  
2/27/2024 10:02 AMamy.boll@inl.gov
2024 DOE-NE
ART GCR
Annual Review
July 16-18, 2024
https://art.inl.gov/Rotating%20Graphics/2024%20DOE-NE%20ART%20GCR%20Annual%20Review_July%2016-18.pdf
63591.png63591 R1_AGC-4 Disassembly Report
  
2/27/2024 10:03 AMamy.boll@inl.gov
The ART Graphite Research and Development program is currently measuring irradiated material property changes in several grades of nuclear graphite to predict behavior and operating performance within the core of new high-temperature reactor designs.
The ART Graphite Research and Development program is currently measuring irradiated material property changes in several grades of nuclear graphite to predict behavior and operating performance within the core of new high-temperature reactor designs.
https://www.osti.gov/biblio/1996370
71441_Kernel Buffer.png71441_Kernel Buffer Volume Fraction Margin of the AGR Designed Fuel Particle
  
2/26/2024 6:55 PMamy.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
74748.png74748_FY-23 Status Report on the Development of New ASME Section III, Division 5 Class B Rules
  
2/27/2024 10:03 AMamy.boll@inl.gov
ASME Boiler and Pressure Vessel Code, Section III, Division 5, Class B rules to address the gaps identified for high temperature reactor designs.
ASME Boiler and Pressure Vessel Code, Section III, Division 5, Class B rules to address the gaps identified for high temperature reactor designs.
https://www.osti.gov/biblio/2000864
ART FACT SHEET.pngAdvanced Reactor Technologies Gas-Cooled Reactors
  
2/27/2024 10:03 AMamy.boll@inl.gov
Work is primarily perfromed at Argonne, Oak Ridge, and Idaho national laboratories. Including participants from industry and
universities.
The mission of the Department of Energy
Nuclear Energy's (DOE-NE) Advanced Reactor
Technologies (ART) program is to develop
new and advanced reactor designs and
technologies that strengthen reactor
competitiveness and support the nation's
energy, environmental, and national security
needs.
ART is primarily performed at the Idaho,
Argonne, and Oak Ridge national laboratories
and includes participants from industry and
universities. The program also participates in
international collaborations to foster and
leverage international reactor, technology,
research and development.
https://art.inl.gov/Rotating%20Graphics/ART%20Factsheet_July%202023_final.pdf
  
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.
  
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
  
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