Published October 2018 | Version v1
Journal article

Oxygen diffusion in liquid (over)stoichiometric corium

  • 1. CEA, DEN, DTN/SMTA/LEAG, Cadarache, F-13108 Saint-Paul-lez-Durance (France)
  • 2. CEA, DEN, DTN/SMTA/LMAG, Cadarache, F-13108 Saint-Paul-lez-Durance (France)

Description

Highlights: • Liquid corium oxidation may impact FCI phenomena like steam explosion. • Modelling of 1-D oxygen diffusion in liquid corium droplets is performed. • CALPHAD-based thermodynamic calculations are coupled with oxidation kinetics. • Typical oxidation transient times are determined for various corium droplets. • Transient analysis highlights original internal mass transfer phenomena. - Abstract: Within the framework of pressurized water reactor severe accidents, the ICE research program is devoted to studies on a variety of fundamental mechanisms involved in Fuel-Coolant Interaction (FCI). Among them, the oxidation of liquid corium is expected to impact the premixing/fragmentation stage, thus possibly influencing the subsequent steam explosion. As a first step towards the exhaustive description of oxidation phenomena occurring in typical FCI layouts, the 1-D oxygen diffusion in liquid (over)stoichiometric spherical corium droplets is investigated in this article. A mesoscopic description is adopted, based on the evolution of oxygen concentration cO, depending on space, time, corium composition and temperature. The underlying physical model is coupled with CALPHAD-based thermodynamic calculations. An asymptotic analytical solution is first determined, assuming that the apparent diffusion coefficient DO does not depend on cO. Then, the general variational form of governing equations is derived, leading to the implementation of a related numerical approach using the finite-element method, in COMSOL® software. This numerical approach is first benchmarked with the analytical calculation, and then extrapolated to the more general case where DO varies with cO. Finally, some case studies representative of FCI issues are selected, in order to determine typical oxygen diffusion transient times within a variety of liquid corium droplets.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2018.06.027

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2018.06.027;
PII
S0029549318301912;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
337
Journal Page Range
p. 148-160
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Notes
© 2018 Elsevier B.V. All rights reserved.