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INL Advanced Reactor Technologies

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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News Highlights


HTR History.JPGHistory of High Temperature Reactors
9/20/2019 10:14
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.
PettiDavid (002).jpgDavid Petti Recognized by Congress
9/20/2019 1:00
Congress recognized David Petti career accomplishments.
Dave Petti, Nuclear Fuels and Materials division director, recently announced his retirement. To recognize his career accomplishments, Mike Crapo, along with Jim Risch and Mike Simpson, read a tribute to Dave in Congress.
Special_Award.pngFraming Safety Renewing Safety Standards
9/20/2019 1:03
Three INL researchers awarded by ANS for their enhancement of regulatory framework for advanced nuclear reactors.
Framing Safety Renewing Safety Standards
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.
Dave Petti is in Europe this week presenting on a new MIT report he led that found on the role of energy in a carbon-constrained world.
To read full article Massachusetts Institute of Technology
The US Department of Commerce should not place any import limits or restrictions on uranium from Canadian producer Cameco, the company said in its submission to the DOC's ongoing Section 232 investigation. The comment period on the investigation has now closed.
What is TRISO Fuel? 

There’s a lot of buzz around advanced nuclear. Enter TRISO fuel the most robust nuclear fuel on earth.



ICAPP 2020 208246Mar 15TrueICAPP provides a forum for leaders of the nuclear community to exchange information, present results from their work, review the state of the industry, and discuss future directions and needs for the deployment of new nuclear power plant systems around the world. 1/20/2020 7:41:14 PM6
IAEA Graphite Creep CRP meeting208249April 1True1/20/2020 7:29:16 PM
2020 ANS 208248June 7True2020 ANS Annual Meeting1/20/2020 7:43:10 PM
Program Review Meeting208466July 15True2020 GCR Program review meeting1/22/2020 4:10:09 PM
Independence Day208254July 4TrueCommemorating the Declaration of Independence of the United States, on July 4, 17761/20/2020 7:57:45 PM
ANS Winter Meeting208250Nov 15TrueThe ANS Winter Meeting and Nuclear Technology Expo is the premier North American nuclear science and technology conference and it will be one of the year’s most exciting and informative educational and networking events for attendees from every facet of nuclear science and technology. 1/20/2020 7:29:45 PM
INL Curtailment196515Dec 25TrueINL Curtailment9/20/2019 2:38:16 PM53