Database of measured isotopic concentrations of spent nuclear fuel, with operational histories and design data.
(Spent Fuel Isotopic Composition) is a relational database designed
to facilitate the search and visualisation of experimental assay data of spent nuclear fuel. It allows the user to access, plot and export isotopic composition data, reactor operational histories
and relevant design data relating to spent fuel samples. The database can be queried using different search criteria.
The data in SFCOMPO come from fuel samples irradiated in power reactors which
have been experimentally measured in the past 50 years. SFCOMPO 2.0 offers a consistent and standardised approach to store,
retrieve and compare different datasets from different post-irradiation experimental campaigns. Whenever it has been possible, original experimental lab reports or original publications
have either been linked directly from the application, or are referenced.
The aim of SFCOMPO 2.0 is to present the user of assay data with a referenced, standardised, cross-checked source of published experimental data for the use of assay data
SFCOMPO 2.0 is developed by the Nuclear Energy Agency (NEA) in close collaboration with Oak Ridge National Laboratory (ORNL).
The data in SFCOMPO was captured by a collaboration between ORNL, NEA and Universidad Politecnica de Madrid, and has undergone an iterative review process by the NEA Expert Group on Assay Data of Spent Nuclear Fuel
(EGADSNF). SFCOMPO-2.0 is distributed free of charge.
SFCOMPO 2.0 was publicly released in June 2017. It contains experimental data coming from 44 different reactors of 8 different international types, currently representing 750 fuel samples.
The database currently contains more than 24,000 measurement entries.
The data in SFCOMPO 2.0 have been independently reviewed for consistency with the experimental reports but has not been formally evaluated.
Any errors in measurements, omissions, or inconsistencies in the original reported data may be reproduced in the database.
Therefore it is important that any user of the data for code validation consider and assess the potential data deficiencies.
The evaluation of assay data will provide a more complete assessment and may result in the development of benchmark specifications and measurement
data in cases of high quality experiments. Evaluations are a multi-disciplinary effort involving reactor specialists, modeling and simulation experts,
and radiochemistry experts.
SFCOMPO 2.0 contains only openly accessible, published experimental assay data. The data in SFCOMPO 2.0 are presented as published,
and have been cross-checked with special care to avoid transcription errors. In spite of this careful review, some errors may still exist. The user is directed to the original reference reports for final verification. Your feedback is welcome and encouraged.
SFCOMPO 2.0 is developed in Java and is platform independent. SFCOMPO 2.0 can be used with Java version 6 or later, however, the use of the latest Java version is recommended.
Citing SFCOMPO 2.0
F. Michel-Sendis et al. (in publication process) "SFCOMPO-2.0: An OECD NEA Database of Spent Nuclear Fuel isotopic Assays, Reactor Design Specifications and Operating Data",
Annals of Nuclear Energy, 2017 (expected).
I. Gauld et al. (in publication process) "Integral Nuclear Data Validation Using Experimental Spent Nuclear Fuel Compositions",
Journal of Nuclear Engineering and Technology, September 2017 (expected).
F. Michel-Sendis, I. Gauld, M. Bossant, N. Soppera: "A New OECD/NEA Database of nuclide compositions of spent nuclear fuel", Proceedings of the PHYSOR 2014 International Conference, Kyoto, Japan, October 2014.