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Molten Salt Reactor Training Materials
November 7-8, 2017

The MSR presentations are available at overall package number is ML17331B100, and the specific modules are listed in the following table. 
Click on the NRC Accession Number to go directly to the presentation.

​MRS Training Module Title
​NRC Accession

​Module   1 - History, Background and Current MSR Developments
​Module   2 - Overview of MSR Technology and Concepts
​Module   3 - Overview of Fuel and Coolant Salt Chemistry and Thermal Hydraulics
​Module   4 - MSR Neutronics
​Module   5 - Materials
​Module   6 - Systems and Components
Module   7 - ​Overview of MSR Instrumentation
​Module   8 - Fuel Cycle and Safeguards
​Module   9 - Operating Experience
​Module 10 - Safety Analysis and Design Requirements
Module 11 - ​Regulatory Issues and Challenges
​Module 12 - MSR Development and R&D Issues

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