SFCOMPO 2.0 (Spent Fuel Isotopic Composition)

Ongoing

View of SFCOMPO 2.0 application. Image: NEA.

Database of measured isotopic concentrations of spent nuclear fuel, with operational histories and design data

SFCOMPO 2.0, 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 evaluators.

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), then renamed into SFCOMPO Technical Review Group. SFCOMPO-2.0 is distributed free of charge.

Disclaimer

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.

System requirements

SFCOMPO 2.0 was 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., "SFCOMPO-2.0: An OECD NEA Database of Spent Nuclear Fuel isotopic Assays, Reactor Design Specifications and Operating Data", Annals of Nuclear Energy 110, 779-788 (2017), www.sciencedirect.com/science/article/pii/S0306454917302104.
I. Gauld et al., "Integral Nuclear Data Validation Using Experimental Spent Nuclear Fuel Compositions", Journal of Nuclear Engineering and Technology 49.6, 1226-1233 (2017), www.sciencedirect.com/science/article/pii/S1738573317303054.
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, dx.doi.org/10.11484/jaea-conf-2014-003.

Contact

SFCOMPO Team

Activities

results

Database for ICSBEP (DICE)

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) released the first version of the Database for the International Handbook of Evaluated Criticality Safety Benchmark Experiments (DICE) in 2001.

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International Criticality Safety Benchmark Evaluation Project (ICSBEP)

The primary purpose of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) is to compile critical and subcritical benchmark experiment data into a standardised format that allows criticality safety analysts to easily use the data to validate calculation tools and cross-section libraries.

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International Reactor Physics Handbook Database and Analysis Tool (IDAT)

The IRPhEP Database and Analysis Tool (IDAT) was first released in 2013 and is included on the IRPhE Handbook DVD. This database and corresponding user interface allows easy access to handbook information. Selected information from each configuration was entered into IDAT, such as the measurements performed, benchmark values, calculated values and materials specifications of the benchmark. In many cases this is supplemented with calculated data such as neutron balance data, spectra data, k-eff nuclear data sensitivities, and spatial reaction rate plots.

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Technical Review Group for the International Assay Data of Spent Nuclear Fuel Database (TRG SFCOMPO)

The Technical Review Group (TRG) for the International Assay Data of Spent Nuclear Fuel Database (SFCOMPO) lies under the direction of the Working Party on Nuclear Criticality Safety (WPNCS).

Working Party on Nuclear Criticality Safety (WPNCS)

The Working Party on Nuclear Criticality Safety (WPNCS) deals with technical and scientific issues relevant to criticality safety. Specific areas of interest include (but are not limited to) investigations of static and transient configurations encountered in the nuclear fuel cycle. These include fuel fabrication, transport and storage.

See

Database of measured isotopic concentrations of spent nuclear fuel, with operational histories and design data

Contents

Disclaimer

System requirements

Citing SFCOMPO 2.0

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