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)
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. 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)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 52106013
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; COMPUTERIZED SIMULATION; CRACK PROPAGATION; CRACKS; FINITE ELEMENT METHOD; IODINE; IRRADIATION; NEUTRONS; VAPORS; ZIRCALOY 4
- Descriptors DEC
- ALLOYS; ALLOY-ZR98SN-4; BARYONS; CALCULATION METHODS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEPOSITION; ELEMENTARY PARTICLES; ELEMENTS; FERMIONS; FLUIDS; GASES; HADRONS; HALOGENS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; MATHEMATICAL SOLUTIONS; NONMETALS; NUCLEONS; NUMERICAL SOLUTION; SIMULATION; SURFACE COATING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 22 refs., 16 figs.