Published June 2021 | Version v1
Report

3D Modeling of PCI-SCC in Alcyone Fuel Performance Code

  • 1. CEA, Cadarache (France)
  • 2. CEA, Saclay (France)

Description

The paper presents the latest developments in ALCYONE fuel performance code concerning the modelling of pellet cladding interaction (PCI) and clad failure caused by iodine-induced stress corrosion cracking (I-SCC). ALCYONE includes a 3D finite element model to describe the thermo-mechanical behaviour of a fuel pellet fragment and its frictional contact with the surrounding cladding. ALCYONE provides a precise evaluation of the temperature and stress state across the clad wall during power transients that can lead to clad failure by I-SCC. The application of an I-SCC crack propagation model in the 3D simulations of PCI with ALCYONE is of primary interest in the paper. A series of power ramps performed in the OSIRIS materials test reactor are analyzed. The calculated times to failure by PCI induced I-SCC are compared to in-reactor measurements, which shows a good agreement each other. Advanced simulations of non-failed rods during power ramps are then proposed to analyze the potential reasons for the clad resistance to I-SCC in relation to the build-up of a suitable chemical environment at the clad inner wall. The simulations include thermodynamic equilibrium calculations of the uranium dioxide matrix with the fission products (FP) of interest for I-SCC (I, Cs, Te) that are coupled to the fission gas release model (MARGARET) of ALCYONE. They illustrate the importance of a correct assessment of the chemical conditions at the triple point with respect to I-SCC crack propagation modelling. (author)

Part of:
Progress on Pellet–Cladding Interaction and Stress Corrosion Cracking. Experimentation, Modelling and Methodologies Applied to Support the Flexible Operation of Nuclear Power Plants. Report of a Technical Meeting

Additional details

Publishing Information

ISBN
978-92-0-116521-3
Imprint Title
Progress on Pellet#En Dash#Cladding Interaction and Stress Corrosion Cracking. Experimentation, Modelling and Methodologies Applied to Support the Flexible Operation of Nuclear Power Plants. Report of a Technical Meeting
Imprint Pagination
314 p.
Journal Page Range
p. 213-225
ISSN
1011-4289
Report number
IAEA-TECDOC--1960

Conference

Title
Experimentation, Modelling and Methodologies Applied to Support the Flexible Operation of Nuclear Power Plants
Acronym
Technical Meeting on Progress on Pellet Cladding Interaction and Stress Corrosion Cracking
Dates
8-11 Oct 2019
Place
Aix-en-Provence (France)

Optional Information

Notes
22 refs., 11 figs.