You may be trying to access this site from a secured browser on the server. Please enable scripts and reload this page.
Turn on more accessible mode
Turn off more accessible mode
Skip Ribbon Commands
Skip to main content
Turn off Animations
Turn on Animations
Gateway for Accelerated Innovation in Nuclear
What is GAIN?
What's New in GAIN?
D.O.E. / National Laboratories
GAIN Impact Video
GAIN Monthly Highlights
Nuclear Science User Facilities (NSUF)
Advanced Nuclear Technology Development FOA DE-FOA-0001817
Technology Commercialization Fund
Small Business Innovation Research (SBIR) FOA
ARPA-E | DOE $24 Million in Funding
FY 2018 CINR FOA
Versatile Test Reactor
Fast Reactor Technology
High Temperature Gas Reactor Technology
Advanced Nuclear Fuel Technologies Program
Advanced Reactor Technologies (ART) Program
Databases & Documents
Light Water Reactor Sustainability (LWRS) Program
National Lab Capabilities
Nuclear Science User Facilities (NSUF)
Site Permit Process
Nuclear Regulatory Commission
NSUF GAIN Industry Advisory Meeting - October 2018
Advanced Manufacturing for Nuclear - December 2018
Economics-Based R&D for Nuclear Power Construction - January 2019
GAIN Advanced Fuels Workshop - March 2019
Past Workshop Presentations
MODELING AND SIMULATION
Advanced Reactor Tools
Third Way - Nuclear Reimagined
Sodium-cooled Fast Reactor (SFR) Technology Seminar
February 18, 2015
Sodium Fast Reactor Technology Seminar Agenda
Sodium-cooled Fast Reactor Technology and Safety Overview
EBR-II Operating and test Experience-Sackett-1996
The Experimental Breeder Reactor number 2 (EBR-II) has operated for 30 years, the longest for any liquid metal cooled reactor (LMR) power plant in the world.
EBR-II Operating and Test Experience with EBR-II Prototype
Bibliography of Publications on Experimental Breeder Reactor No. II (EBR-II)
This document is the fifth revision of the bibliography of publications on EBR-II that was originally published in 1979. It lists all such publications dated through August 1992.
Fast Reactor Technology Information
The interim Fast Reactor (FR) Technology Information List provides access to the first set of cataloged FR documents available on OSTI. By downloading the Excel spreadsheet, you will have access to individual links to each legacy file. The file will be updated periodically as we work through the continuing catalog process with OSTI. Please direct questions through
GAIN-DOE Fast Reactor Tech Rpts Public 16Feb17
Fast Flux Test Facility
The Fast Flux Test Facility (FFTF) is the most recent liquid-metal reactor (LMR) to operate in the United States (1982 to 1992) and played a key role in Liquid Metal Fast Breeder Reactor (LMFBR) development and testing activities. In addition to irradiation testing capabilities, FFTF provided long-term testing and evaluation of plant components and systems for LMFBRs. The technology employed in designing and constructing this reactor, as well as information obtained from tests conducted during its operation could be helpful in advanced reactor designs. As legacy information becomes available, it will be posted in the link below.
Fast Flux Test Facility Documents
TREAT Experimental Relational (TREXR) Database
The TREAT Experimental Relational (TREXR)
is now open to new users. TREXR is an organized, searchable collection of information describing the hundreds of experiments conducted on nuclear reactor fuels in the Transient Reactor Test (TREAT) facility beginning in 1960. Experiments investigated the response of nuclear fuel samples to accident-type conditions; the results support the design of safer nuclear reactors. For more information about the TREXR database, please visit the site's "
" page. US citizens may apply for a collaborator account to access the database contents using the blue button on the "
For current information on the
Sodium (Na) System and Component Reliability Database (NaSCoRD)
The Sodium (Na) System and Component Reliability Database includes reliability data from the Experimental Breeder Reactor II (EBR-II), Fast Flux Test Facility (FFTF), and Joyo reactors and multiple non-nuclear test facilities. This includes a record of component design and performance documentation across various systems that used sodium as a working fluid but was lost by its US custodian in the 1990s. The restructured data and capabilities gained allow the DOE complex and the domestic sodium industry to understand how previous systems were designed and built and then use this information to improve the design and operations of future systems. Instructions to access the database are available on the