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​           Databases & Documents

The GAIN Legacy Document Project was initiated in 2016, after the advanced nuclear industry identified the access to legacy documents as one of the top four, cross-cutting needs critical to the commercialization of advanced reactor technologies.

Legacy Documents, as the name suggests, are the recorded legacy of nuclear research performed within the DOE Laboratory Complex. GAIN works with industry to identify data or documents that they need.  From there, GAIN tailors the approach to locate the documents and get them to industry. This may involve scanning hard copies, updating classification reviews, collaborating with the document owner, etc.  

Decades of past nuclear research is extremely valuable because many of the experimental results cannot be replicated because the facilities that generated the original data no longer exist. By leveraging the knowledge of the past, the current and future nuclear industry will shorten development life cycles and decrease costs.

​If you need assistance regarding legacy documents, please reach out to Holly Powell at​.

​​​​Databases of Experimental​ Information


​​Status (22Jan2021)
TREAT Experiment Relational D​​atabase


External access available by appli​cation
Sodium System & Component Reliability Database
External access available by application
Phase ​II Complete – FY20
EBR-II Transient Testing Database
External access available by application
EBR-II Metallic Fuel Irradiation Database

External access available by application
Data for U-Zr fuel type employed in commercial designs being qualified in accordance with NRC approved QAPP
Passive Safety Testing & Metal Fuel Irradiation Database

External access available by application.
Send request to contacts -​
Out of Pile Transient Testing Database
External access available by application

​EBR-II and FFTF Metal Fuel Experiment PIE Data

​Complete FY21
Organized effort to supplement the FIPD and FFTF Databases.  
Molten Salt Reactor Component Reliability Database

​Under Construction - Available FY21
Currently being populated with operations, maintenance, and experimental data. 
Nuclear Data Management and Analysis Systems

External access available by application
Database Summaries

TREAT Experimental Relational (TREXR) Database
The TREAT Experimental Relational (TREXR) Database 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 "about" page. US citizens may apply for a collaborator account to access the database contents using the blue button on the "login" page.
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 NaSCoRD website.
NDMAS (Nuclear Data Management and Analysis System)
NDMAS comprises databases, a team of data scientists,  and web-based tools for analysis and display of data from INL's TRISO fuel and graphite material research programs. Access to NDMAS from outside INL is generally provided on a per-project basis, by permission of the relevant project manager. Please visit this site to access public and access-controlled pages.​


U.S. Industry Opportunities for Advanced Nuclear Technology Development Phase III (Technical Report)
December 2021
This is the third phase of a work scope which has been focused on providing a framework for and preserving key experimental programs and experiences which are critical to the licensing basis of currently operating nuclear reactors or which could be used in the safety basis for the next generation of reactors. The first phase of this effort, documented in Phase I, focused on compiling a list of key experimental programs through an international survey of reactor safety professionals working in licensing, design, and academia. The second phase in this effort, documented in Phase II, focused on creating a searchable database framework in which to organize the results from the international survey and to perform detailed research on several key programs to provide the framework for how to categorize the references which could be located. The purpose of the third phase is to perform a high-level research effort on each experiment/experience and to determine if sufficient data, reports, and results have already been captured to consider the program archived for future generators of nuclear professionals.

FAI/21-1065 Final Report-U.S. Industry Opportunities for Advanced Nuclear Technology Development Phase III

Nuclear Archival Electronic Database (NAED)
U.S. Industry Opportunities for Advanced Nuclear Technology Development Phase II (Technical Report)
April 21, 2021
This limited scope study aims at preserving the results of experimental programs for the safety of light water cooled and advanced reactors by locating and documenting, to the extent possible, where the experimental test information for these programs has been archived. The Light Water Reactor Data Preservation Activity Team initially identified seven (7) experimental programs, exceeding the required five (5) in the scope of work, which were determined to be “at risk" of potentially losing valuable data. The seven (7) experimental programs/subject areas identified are (descriptions of each experiment/experience are provided in Section 3.0): 1. FERMI-1 Reactor Accident 2. Fission Product Behavior During the In-Pile Severe Fuel Damage Test SFD I-4 3. Containment Iodine Computer Code Exercise Based on Radioiodine Test Facility (RTF) Experiment 4. Wide Range Piping Integrity Demonstration (WIND) Project 5. Iodine Chemical Research in Canada 6. High Temperature Fission Product Chemistry and Transport in Steam 7. Anything related to radioactive Methyl Iodide.
U.S. Industry Opportunities for Advanced Nuclear Technology Development
October 2019​
Virtually all the operating nuclear power plants in the United States were designed, built and licensed before 2000. While many of these plants went through the license extension evaluations in that time frame, only two designs have been going through the original licensing process after that date. An unfortunate result of this is that many of those individuals involved in the design, construction, licensing and operation of these plants are no longer in the work force and many of the important experimental facilities and individu​als who performed the experimental programs are also no longer available. In fact, much of the experimental data and in some cases the experimental test reports are not available or difficult to locate. This report documents a process to archive important experimental data and provides a demonstration of how the archival status of experiments can be characterized and archived for different levels of experimental documentation.
FAI/19-0715 Final Report-U.S. Industry Opportunity for Advanced Nuclear Technology Development
---------------------------------------------------------------------------------------------------------------------------------------------------Transatomic Power Corporation Passes the Torch
December 18, 2018
Like many companies who work with the GAIN initiative to transform the modern nuclear landscape, Transatomic Power Corporation (TAP) accepted the risks associated with being a "start-up."   The tremendous technical work and social awareness that TAP contributed to the advanced nuclear industry should not be diminished.  It is clear that they were motivated in large part by the desire to make the world a cleaner, safer place through the development of their reactor concept. The hope of the GAIN initiative and TAP is that this fundamental work will continue to support the rapidly evolving nuclear community.  This is reflected in the TAP decision to open source their technology for all to use. The GAIN initiative is pleased to have the privilege of facilitating access to the TAP legacy in support of this ideal.
FIPD: EBR-II Fuels Irradiation & Physics Database
September 18, 2017
The DOE Advanced Reactor Technology program has supported e fforts to recover and preserve metallic fuel data generated throughout the US sodium cooled fast reactor program (SFR). Those efforts have been focused on establishing databases of the experimental data that were mainly generated during the Integral Fast Reactor program including data generated at EBR-II, FFTF, and TREAT reactors, as well as out of pile data. The data is essential for future-licensing activities of metallic fuel based advanced fast reactors. This report describes the EBR-II Fuels Irradiation & Physics Database (FIPD). It covers the scientific knowledge available in the database, the logical storage of the data in the database, and the web interface used to access the data. The report also covers the QA plan (SQAPP) developed to cover all aspects of the FIPD system. Summaries of activities from previous years, the current fiscal year (FY17), and future plans are also provided.
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
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.
​Molten Salt Reactor Technology Information
The interim MSR Technology Information List provides access to the first set of cataloged MSR 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
Pre-Licensing Evaluation of Legacy SFR Metallic Fuel Data
September 16, 2016
The US sodium cooled fast reactor (SFR) metallic fuel performance data that are of interest to advanced fast reactors applications, can be attributed mostly to the Integral Fast Reactor (IFR) program between 1984 and 1994. Metallic fuel data collected prior to the IFR program were associated with types of fuel that are not of interest to future advanced reactors deployment (e.g., previous U-Fissium alloy fuel). The IFR fuels data were collected from irradiation of U-Zr based fuel alloy, with and without Pu additions, and clad in different types of steels, including HT9, D9, and 316 stainless-steel. Different types of data were generated during the program, and were based on the requirements associated with the DOE Advanced Liquid Metal Cooled Reactor (ALMR) program.
Pre-Licensing Evaluation of Legacy SFR Metallic Fuel Data Report
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. 
Bibliography of Publications on Experimental Breeder Reactor No. II (EBR-II)
August 1992
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.