IAEA’S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS

ikoleta Morelová, Vladimir Kriventsev, T. Sumner, A. Moisseytsev,Florent Heidet, D.W. Wootan, Andrew M. Casella, J.V. Nelson, I. Di Piazza, Houcine Hassan, Pierdomenico Lorusso,Daniele Martelli, Xiaoyan Yang, Jin Wang,Daogang Lu,Dalin Zhang, A. Gerschenfeld, S. Kliem, E. Fridman, A. Rineiski, Natesan Kumaresan,Fabio Giannetti, A. Petruzzi,Masaaki Tanaka,Ji-Young Jeong, Jiang Hong, M.M. Stempniewicz, S. V. Tsaun, A. V. Volkov,Janne Wallenius, Carlo Fiorina,Konstantin Mikityuk, Rodolfo Vaghetto, Olu Omotowa, Joseph Kelly, J. W. Lane

Proceedings of the International Conference on Nuclear Engineering, ICONE（2023）

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摘要

A Coordinated Research Project on “Benchmark Analysis of FFTF Loss of Flow Without Scram Test” was launched by the International Atomic Energy Agency (IAEA) in 2018. A series of passive safety tests were conducted from 1980-1992 at the Fast Flux Test Facility (FFTF), 400 MW(th) liquid sodium cooled nuclear test reactor owned by U.S. Department of Energy (DOE) to demonstrate the potential of FFTF to survive severe accident initiators with no core damage. Amongst these tests was a series of Loss of Flow Without Scram (LOFWOS) tests from power levels up to 50%, also commonly referred to as Unprotected Loss of Flow (ULOF) tests, which were studied in the IAEA CRP. The data were provided by the Argonne National Laboratory (ANL) and Pacific Northwest National Laboratory (PNNL).

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