First Research Coordination Meeting on Benchmark Analysis of Fast Flux Test Facility (FFTF) Unprotected-Loss-of-Flow Test

This is the first meeting for the IAEA Coordinated Research Project (CRP) which will focus on a benchmark analysis of one of the passive safety demonstration tests performed at the Fast Flux Test Facility (FFTF), a 400 MW (Th) sodium cooled nuclear test reactor owned by the US Department of Energy.

The Pacific Northwest National Laboratory (PNNL) and the Argonne National Laboratory (ANL) jointly proposed this CRP to the IAEA in 2017, offering to share experimental test data with the fast reactor community through the IAEA. At its 50th meeting in May 2017, the Technical Working Group on Fast Reactors (TWG-FR), which provides advice and support to IAEA’s programme implementation in this area, endorsed the CRP.

This CRP is aimed at improving IAEA Member States' analytical capabilities in the field of fast reactor simulation and design. The project will contribute to strengthening the cooperation between Member States in achieving advances in fast reactor technology development through an international collaborative benchmark. The CRP will also support training of the next generation of fast reactor professionals.