| Reports
Fast Reactor Technology Training Materials June 5, 2019 The NRC contracted with Argonne National Laboratory (ANL) to develop and present a training course on fast reactors. The course provides background on various fast reactor concepts presently under development, including a history of earlier fast reactor projects, descriptions of conceptual designs, and expected technical and regulatory challenges.
Pre-Licensing Evaluation of Legacy SFR Metallic Fuel Data December 21, 2017 The DOE Advanced Reactor Technology program has supported efforts 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 are essential for future-licensing activities of metallic fuel based advanced fast reactors. This report describes the available historical metallic fuel data, past use of the data to support licensing related activities, as well as summary of a plan to qualify those data so it can be used in future licensing activities. This plan is applicable to data from those different sources of metallic fuel data. An example of the plan implementation with a limited set of experimental data is provided to demonstrate the qualification process. While the QA plan implementation described in the report was focused on data from the Alpha Gamma Hot Cell Facility (AGHCF) at Argonne, as an example, the QA plan can be applied to data generated at other facilities. The plan is applicable to all historical metallic fuel data that are pertinent to future licensing of SFRs.
FIPD: EBR-II Fuels Irradiation & Physics Database September 18, 2017 The DOE Advanced Reactor Technology program has supported efforts 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 aspectf of the FIPD system. Summaries of activities from previous years, the current fiscal year (FY17, and future plans are also provided.  FIPD: EBR-II Fuels Irradiation Physics Database
Sodium-cooled Fast Reactor (SFR) Technology Seminar February 18, 2015
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.
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. 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.
 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. |
| Databases 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. For current information on the TREAT facility click here.
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.
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