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Databases  &  Documents

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.
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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.

















































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.
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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.
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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.inl.gov.
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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.
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​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 gain.inl.gov.
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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
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EBR-II Operating and test Experience-Sackett-1996
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. 
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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.