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)
Additional details
Identifiers
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)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 52106017
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; COMPUTERIZED SIMULATION; CRACK PROPAGATION; CRACKING; FINITE ELEMENT METHOD; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL ELEMENT FAILURE; FUEL PELLETS; IODINE; MATERIALS TESTING REACTORS; MATRICES; NUCLEAR FUELS; PERFORMANCE; STRESS CORROSION; THERMODYNAMICS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; CHEMICAL REACTIONS; CORROSION; DECOMPOSITION; DEPOSITION; ELEMENTS; ENERGY SOURCES; FAILURES; FUELS; HALOGENS; IRRADIATION REACTORS; ISOTOPES; MATERIALS; MATHEMATICAL SOLUTIONS; NONMETALS; NUMERICAL SOLUTION; OXIDES; OXYGEN COMPOUNDS; PELLETS; PYROLYSIS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; SIMULATION; SURFACE COATING; THERMOCHEMICAL PROCESSES; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 22 refs., 11 figs.