Published June 2021 | Version v1
Report

Experimental Characterization and Modeling of I-SCC of Zirconium Alloy in an Iodine Vapor Environment

  • 1. CEA, Saclay (France)
  • 2. CEA, Cadarache (France)
  • 3. EDF/R&D, Moret-Sur-Loing (France)
  • 4. EDF/DT, Villeurbanne (France)
  • 5. FRAMATOME, Lyon (France)

Description

The I-SCC behaviour of cold-worked stress-relieved (CWSR) zircaloy-4 was investigated with internal pressure tests in inert and vapor iodine environments. I-SCC susceptibility was established from tests on un-irradiated and neutron-irradiated cladding tubes. I-SCC crack propagation rates were evaluated from tests on pre-cracked tubes. The internal pressure tests conducted on un-irradiated CWSR zircaloy-4 cladding tubes in a gaseous iodine environment were used to investigate the influence of test temperature (320°C, 350°C, or 380°C) on the I-SCC process. The experimental results exhibited an apparent threshold hoop stress, below which I-SCC does not occur. The tests were simulated by finite element models using a specific viscoplastic constitutive equation. The I-SCC initiation and time-to-failure predictions were modelled by a Kachanov's damage law written with a hoop stress threshold. In the simulations, the Kachanov's law can be used in post-treatment of calculations or coupled with the viscoplastic constitutive equation for the cladding in order to simulate both the initiation and the propagation of the I-SCC crack. The coupling was implemented in the CAST3M finite element code using either massive elements or Cohesive Elements. (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. 178-191
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., 16 figs.