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• W2032057741 abstract "AbstractIn the first Phebus test, 20, one meter long, lightly irradiated UO 2 fuel rods and a central Ag–In–Cd control rod wereheated by fission power to an estimated 3000°C. In this paper results are reported for the composition of the moltencorium pool in the lower part of the test assembly and deposits of released core material in the vertical line. Theexamination techniques used comprised optical microscopy, scanning electron microscopy, X-ray microbeam analysis,inductively coupled plasma mass spectroscopy, X-ray di•raction and c-spectroscopy. The matrix of the corium poolwas a single phase of composition (U 0:50 Zr 0:47 Fe 0:02 Y 0:01 )O 2 x . Inclusions in the solidified pool were ReIr alloys, W withminor concentrations of Fe and Ni and spinels of Cr, Fe and Ni. The main constituents of the deposit in the verticalline were Re, Ag, In and Sn. Tin formed a thin layer on the steel surface. Droplets of the corium matrix phase wereembedded in the deposit. Traces of 137 Cs were mainly responsible for the c-activity of the deposit. O 2000 ElsevierScience B.V. All rights reserved.1. IntroductionThe Phebus–FP (fission product) project is managedjointly by the Institut de Protection et Surete Nucl eaire(IPSN), Cadarache, France and the Institute for Sys-tems, Infomatics and Safety Technologies at the Euro-pean CommissionOs Joint Research Centre, Ispra, Italywith contributions from Canada, Japan, South Korea,the USA and, since 1995, Switzerland. The project isdesigned to measure the source-term (mass or activity offission products, activation products and actinides re-leased from a nuclear fuel in a reactor accident) and tostudy the degradation of irradiated UO" @default.
• W2032057741 created "2016-06-24" @default.
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• W2032057741 date "2000-04-01" @default.
• W2032057741 modified "2023-09-22" @default.
• W2032057741 title "Examination of melted fuel rods and released core material from the first Phebus-FP reactor accident experiment" @default.
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• W2032057741 doi "https://doi.org/10.1016/s0022-3115(99)00257-3" @default.
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