Size-distribution of irradiation-induced dislocation-loops in materials used in the nuclear industry
- 1. Department of Materials Physics, Eötvös University Budapest, PO Box 32, H-1518 (Hungary)
- 2. Materials Performance Centre, The University of Manchester, M13 9PL (United Kingdom)
Description
Neutron or proton irradiation induced dislocation loops in Zr and its alloys are usually characterized by electron microscopy methods. In plastically deformed materials X-ray line profile analysis (XLPA) is now a well-established tool to determine dislocation densities (DDs) with excellent agreement between XLPA and TEM analysis. In irradiated zirconium alloys, however, XLPA determined DDs are often considerably larger than those obtained by TEM. In ion irradiated Cu and W it was shown that X-ray diffraction or MD simulations give significantly larger dislocation loop densities than conventional TEM analysis, which suggests that the smallest loops remain undetected by TEM. Based on these results we developed a new methodology to determine power-law size-distributions of irradiation-induced dislocation loops. We assume that only loops larger than a certain threshold are fully counted in TEM micrographs, whereas XLPA detects all the loops in the entire size range. This new analysis procedure shows that in neutron irradiated Zircaloy-2 in the channel-box materials the total DD is larger than in the cladding materials, even though TEM counting shows the opposite. We also found that there is a correlation between the reciprocal square-root of a>-loop DDs and the diameter of a>-loops. Our work shows that irradiation induced loop-formation and irradiation-damage in general can be better determined when we combine TEM investigations with XLPA.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2021.152945Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2021.152945;
- PII
- S0022311521001689;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 550
- Journal Page Range
- vp.
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54019729
- Subject category
- S36: MATERIALS SCIENCE; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- CLADDING; COMPUTERIZED SIMULATION; DENSITY; DISLOCATIONS; IRRADIATION; NEUTRONS; NUCLEAR INDUSTRY; PROTONS; TRANSMISSION ELECTRON MICROSCOPY; X RADIATION; X-RAY DIFFRACTION; ZIRCALOY 2
- Descriptors DEC
- ALLOYS; ALLOY-ZR98SN-2; BARYONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; COHERENT SCATTERING; CORROSION RESISTANT ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DEPOSITION; DIFFRACTION; ELECTROMAGNETIC RADIATION; ELECTRON MICROSCOPY; ELEMENTARY PARTICLES; FERMIONS; HADRONS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INDUSTRY; IONIZING RADIATIONS; IRON ADDITIONS; IRON ALLOYS; LINE DEFECTS; MATERIALS; MICROSCOPY; NICKEL ADDITIONS; NICKEL ALLOYS; NUCLEONS; PHYSICAL PROPERTIES; RADIATIONS; SCATTERING; SIMULATION; SURFACE COATING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Copyright
- Copyright (c) 2021 Published by Elsevier B.V. All rights reserved.