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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62180.pngAGR 5/6/7 Data Qualification Report for ATR Cycles 162B Through 168A
8/19/2021 11:52 AMJodi L. Vollmer
The test train contains five separate capsules that were independently controlled and monitored. Each capsule contains multiple 12.51-mm-long compacts filled with low enriched uranium carbide/oxide tristructural isotropic fuel particles.
AGR 5/6/7 Data Qualification Report for ATR Cycles 162B Through 168A
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.
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
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
The U.S. Department of Energy’s Idaho National Laboratory will produce HALEU for upcoming new reactor demonstrations and for new fuels like CCTE’s ANEEL that will replace older fuels in some existing reactor designs.



INL Curtailment Dec 24-Dec 31151846Dec 24True ​INL Curtailment Dec 24-Dec 31​ 10/21/2021 9:48:54 PM36
34th Regulatory Information Conference101034Mar 9True ​The U.S. Nuclear Regulatory Commission's (NRC's) 34 th Regulatory Information Conference (RIC) being held March 8–10, 2022, will be a hybrid event. The in-person portion will take place at the Bethesda North Marriott Hotel and Conference Center, located at 5701 Marinelli Road, North Bethesda, MD 20852, and an online platform will be available for virtual participation. Regulatory Information Conference | ​ 10/21/2021 9:58:27 PM17