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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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66390_Fuel Performance Modeling Plan to Support the Advanced Gas Reactor Program.PNG66390_Fuel Performance Modeling Plan to Support the Advanced Gas Reactor Program
  
8/26/2024 1:04 PMamy.boll@inl.gov
This report documents the current status of the fuel performance modeling initiative to support the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program in the development of tristructural isotropic (TRISO)-coated fuel particles.
This report documents the current status of the fuel performance modeling initiative to support the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program in the development of tristructural isotropic (TRISO)-coated fuel particles.
https://www.osti.gov/biblio/2335902
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
78112_AGC-4 Specimen Post-Irradiation Examination Data Interim Report.PNG78112_AGC-4 Spcimen Post-Irradiation Examination Data Interim Report
  
8/26/2024 12:50 PMamy.boll@inl.gov
This interim report documents preliminary results of the post-irradiation examination material-property testing from the fourth Advanced Graphite Creep (AGC) experiment campaign, AGC-4, capsule specimens.
This interim report documents preliminary results of the post-irradiation examination material-property testing from the fourth Advanced Graphite Creep (AGC) experiment campaign, AGC-4, capsule specimens.
https://www.osti.gov/biblio/2352601
78846_ Baseline Characterization.PNG78846_Baseline Characterization Baseline Characterization  Database Verification  Report NBG-17 Billet V104
  
8/26/2024 12:25 PMamy.boll@inl.gov
The purpose of this report is to present data collected in the Baseline Graphite Characterization Program, which is directly tasked with supporting the Idaho National Laboratory’s research and development efforts on the ART Program.
The purpose of this report is to present data collected in the Baseline Graphite Characterization Program, which is directly tasked with supporting the Idaho National Laboratory’s research and development efforts on the ART Program.
https://www.osti.gov/biblio/2396823
ART FACT SHEET.pngAdvanced Reactor Technologies Gas-Cooled Reactors
  
4/29/2024 4:52 PMamy.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/Advanced%20Reactor%20Technologies%20Website%20registration%204.29.2024.pdf
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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

 

 

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