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Advanced Reactor Training Materials 
The NRC contracted with the national laboratories to develop and present training courses on:
Molten-Salt Reactors (Oak Ridge National Laboratory) - November, 2017
Fast Reactors (Argonne National Laboratory) - March, 2019
High-Temperature Gas-Cooled Reactors (Idaho National Laboratory) - July, 2019

The courses provide background on various advanced reactor technology concepts presently under development, including a history of earlier projects, descriptions of conceptual designs, and expected technical and regulatory challenges.

Links to the training material are: molten salt reactorsfast reactors, and high-temperature gas-cooled reactors.

Modular HTGR Technology and Safety Design Approach
February 25, 2015
Sodium-cooled Fast Reactor (SFR) Technology Seminar
February 18, 2015


A Regulatory Review Roadmap for Non-Light Water Reactors
December 26, 2017
On December 26, 2017, the NRC staff issued a final document, “A Regulatory Review Roadmap for Non-Light Water Reactors.” This document describes the options available for NRC review of pre-application information and of formal applications. Understanding what options are available and how to choose the best option may be difficult for a designer, especially one that is less familiar with the NRC’s regulatory framework and associated review processes. Preliminary draft versions of the roadmap document and the testing enclosure were previously made publicly available as separate documents and discussed at public meetings with stakeholders. The final, integrated document is available at ADAMS accession number ML17312B567.

If you have any questions about this document, please contact George Tartal, 310-415-0016, at

Nuclear Power Reactor Testing Needs and Prototype Plants for Advanced Reactor Designs
June 14, 2017
The Nuclear Regulatory Commission (NRC) recently issued a preliminary draft document, “Nuclear Power Reactor Testing Needs and Prototype Plants for Advanced Reactor Designs.” This document describes the relevant regulations governing the testing requirements for advanced reactors, describes the process for determining testing needs to meet the NRC’s regulatory requirements, clarifies when a prototype plant might be needed and how it might differ from the proposed standard plant design, and describes licensing strategies and options that include the use of a prototype plant to meet the NRC’s testing requirements.

The document is available in the NRC’s Agencywide Documents Access and Management System at accession number ML17025A353. This preliminary draft document is a first step in communicating with stakeholders about prototype testing for advanced reactors. 

If you have any questions about this draft document, please contact George Tartal, 310-415-0016, at