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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


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
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.
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.
Potential production volume of TRISO fuel for the years 2020-2026 has also been included in the report followed by comparison of TRISO fuel on other parameters such as fuel production reactor ...
Leverages DOE’s +$250M investment in the development of UCO TRISO fuel by advancing an AR that uses this fuel inclusive licensing issues that will benefit all AR projects.
The U.S. Department of Defense wants to build a prototype advanced mobile nuclear microreactor at the Idaho National Laboratory in eastern Idaho, saying they are needed to ensure the military’s energy supply.



2020 ANS Virtual208248June 7True2020 ANS Annual Meeting6/3/2020 3:40:28 PM22
Independence Day208254July 4TrueCommemorating the Declaration of Independence of the United States, on July 4, 17765/19/2020 1:24:10 PM19
Program Review Meeting208466Jul 14True2020 GCR Program review meeting6/3/2020 3:41:41 PM19
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 PM20
INL Curtailment196515Dec 25TrueINL Curtailment9/20/2019 2:38:16 PM76