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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.
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 the key fuel concept for the high-temperature gas-cooled reactors (HTGRs), selected by the US Department of Energy (US-DOE) [1]. A TRISO fuel particle consists of a fuel kernel of UO2 or UCO and multiple coatings of a porous graphite buffer layer, inner pyrolytic carbon (IPyC) layer, silicon carbide layer as the primary pressure vessel, and a dense outer pyrolytic carbon (OPyC) layer.
The objective of this study is to develop a 3D neutron kinetic (NK) and thermal hydraulic (TH) coupled model using the INL developed code RELAP5-3D©/PHISICS to study the load following operation of a Modular High-Temperature Gas-Cooled Reactor (MHTGR).
Today, the U.S. Department of Energy (DOE) announced more than $65 million in nuclear energy research, cross-cutting technology development, facility access, and infrastructure awards for 93 advanced nuclear technology projects in 28 states.



Fuels Program Review Meeting 217156Jul 14Trueregister at (https// 1:10:11 PM
Materials and Methods Program Review Meeting - ( 16TrueRegister at (https// 6/24/2020 1:12:41 PM
Labor Day171524Sept 7True6/23/2020 3:50:18 PM
GAIN-EPRI-NEI Sensor Technologies for Advanced Reactors Workshop171526Sept 22True https// 5:14:03 PM