Investigation of U-Zr-O and Fe-Zr-O systems by a laser heating approach - CEA - Commissariat à l’énergie atomique et aux énergies alternatives Access content directly
Conference Papers Year : 2016

Investigation of U-Zr-O and Fe-Zr-O systems by a laser heating approach

Abstract

During a severe accident in a nuclear reactor, the nuclear fuel (UO$_2$ or MOx) may interact with the Zircaloy cladding and with the metallic structures inside the vessel (spacer grids, neutronic absorbers cladding) forming a solid/liquid mixture called corium. At this stage of the accident, the temperature inside the damaged reactor can exceed 2700K. In this framework, the knowledge of the high temperature properties of corium are paramount for the comprehension of how possible accidental scenarios proceed. In particular, the U-(Pu)-Zr-Fe-O system has been considered in the present study, as a simplified version of the real corium. The aim of this study has been the acquisition of high temperature data on some key sub-systems of corium. This paper is focused on the results obtained on the U-Zr-O and Fe-Zr-O ternary systems. Liquidus and solidus temperatures have been obtained by using the laser heating setup at JRC-ITU.
Fichier principal
Vignette du fichier
201600000004%20annexe.pdf (3.58 Mo) Télécharger le fichier
201600000004 annexe.pdf (3.58 Mo) Télécharger le fichier
Origin : Files produced by the author(s)
Origin : Files produced by the author(s)

Dates and versions

cea-02431805 , version 1 (08-01-2020)

Identifiers

  • HAL Id : cea-02431805 , version 1

Cite

A. Quaini, C. Gueneau, S. Gosse, D. Manara. Investigation of U-Zr-O and Fe-Zr-O systems by a laser heating approach. Youth International Nuclear Congress (IYNC2016), Jul 2016, Hangzhou, China. ⟨cea-02431805⟩

Collections

CEA DEN
33 View
64 Download

Share

Gmail Facebook X LinkedIn More