Materials Map

Discover the materials research landscape. Find experts, partners, networks.

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The Materials Map is an open tool for improving networking and interdisciplinary exchange within materials research. It enables cross-database search for cooperation and network partners and discovering of the research landscape.

The dashboard provides detailed information about the selected scientist, e.g. publications. The dashboard can be filtered and shows the relationship to co-authors in different diagrams. In addition, a link is provided to find contact information.

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The Materials Map is still under development. In its current state, it is only based on one single data source and, thus, incomplete and contains duplicates. We are working on incorporating new open data sources like ORCID to improve the quality and the timeliness of our data. We will update Materials Map as soon as possible and kindly ask for your patience.

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in Cooperation with on an Cooperation-Score of 37%

Topics

Publications (3/3 displayed)

  • 2018ATTILHA A novel experimental setup for thermodynamic and thermophysical properties measurements on nuclear materialscitations
  • 2016High temperature experimental contribution to the thermodynamic modeling of corium poolscitations
  • 2015Experimental investigation and thermodynamic modelling of the in-vessel corium for severe accident studies in PWR reactorscitations

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Chart of shared publication
Bonnet, C.
1 / 6 shared
Gueneau, C.
2 / 13 shared
Gosse, S.
1 / 7 shared
Alpettaz, T.
3 / 12 shared
Quaini, A.
3 / 14 shared
Bonnaillie, P.
1 / 12 shared
Dupin, N.
1 / 6 shared
Guéneau, C.
1 / 16 shared
Poissonnet, S.
1 / 13 shared
Gossé, S.
2 / 16 shared
Manara, D.
1 / 11 shared
Brackx, Emmanuelle
1 / 18 shared
Hodaj, F.
1 / 22 shared
Chart of publication period
2018
2016
2015

Co-Authors (by relevance)

  • Bonnet, C.
  • Gueneau, C.
  • Gosse, S.
  • Alpettaz, T.
  • Quaini, A.
  • Bonnaillie, P.
  • Dupin, N.
  • Guéneau, C.
  • Poissonnet, S.
  • Gossé, S.
  • Manara, D.
  • Brackx, Emmanuelle
  • Hodaj, F.
OrganizationsLocationPeople

document

Experimental investigation and thermodynamic modelling of the in-vessel corium for severe accident studies in PWR reactors

  • Manara, D.
  • Brackx, Emmanuelle
  • Hodaj, F.
  • Lugrin, E. Lizon A.
  • Gueneau, C.
  • Alpettaz, T.
  • Gossé, S.
  • Quaini, A.
Abstract

During a severe accident in a PWR reactor, the oxide nuclear fuel (UO2 or MOX) reacts at high temperature with the zirconium alloy clad and the steel vessel to form a partially or fully molten mixture so-calledin-vessel corium . In such a case, the corium forms a pool in the bottom of the vessel, constituted of two liquid phases, metallic and oxide. The formation of such a configuration of the corium pool is due to the existence of a miscibility gap in the liquid state. The fractions and compositions of these liquid phases have to be well known in order to model the thermal hydraulic properties of the pool. The aim of the present work is to investigate experimentally the thermodynamic properties of the U-Zr-O-Fe system representative for the in-vessel corium to improve the thermodynamic modelling using the Calphad method. Laser heating techniques as well as heat treatments are used to measure solid/liquid transition temperatures and to highlight the miscibility gap in the liquid state. Experimental data are used to assess the thermodynamic properties of this key system. Both experimental and theoretical results will be presented.

Topics
  • impedance spectroscopy
  • zirconium
  • zirconium alloy
  • steel
  • liquid phase
  • CALPHAD