High energy X-ray diffraction study of the relationship between the macroscopic mechanical properties and microstructure of irradiated HT-9 steel
Creators
- 1. University of Illinois at Urbana-Champaign, Urbana, IL 61801 (United States)
- 2. Argonne National Laboratory, Lemont, IL 60439 (United States)
- 3. Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)
- 4. Queen's University, Kingston, ON, K7L 3N6 (Canada)
Description
Samples harvested from an HT-9 fuel test assembly (ACO-3) irradiated for six years in the Fast Flux Test Facility (FFTF) reaching 2–147 dpa at 382–504 °C were deformed in-situ while collecting high-energy X-ray diffraction data to monitor microstructure evolution. With the initiation of plastic deformation, all samples exhibited a clear load transfer from the ferrite matrix to carbide particulate. This behavior was confirmed by modeling of the control material. The evolution of dislocation density in the material as a result of deformation was characterized through full pattern line profile analysis. The dislocation densities increased substantially after deformation, the level of dislocation evolution observed was highly dependent upon the irradiation temperature of the sample. Differences in both the yield and hardening behavior between samples irradiated at higher and lower temperatures suggest the existence of a transition in tensile behavior at an irradiation temperature near 420 °C dividing regions of distinct damage effects. - Highlights: • Irradiation conditions of samples from FFTF range from 2 to 147 dpa at 382–504 °C. • In-situ tensile tests revealed load transfers from ferrite to carbide precipitates. • Level of dislocation density with deformation depends on irradiation temperature. • A transition in tensile behavior appears near an irradiation temperature of 420 °C.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2016.03.023Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2016.03.023;
- PII
- S0022-3115(16)30096-4;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 475
- Journal Page Range
- p. 46-56
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48037164
- Subject category
- S36: MATERIALS SCIENCE; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- ATOMIC DISPLACEMENTS; CARBIDES; COMPUTERIZED SIMULATION; DEFORMATION; DISLOCATIONS; EMBRITTLEMENT; FERRITE; FERRITES; FERRITIC STEELS; FFTF REACTOR; HARDENING; IRRADIATION; MARTENSITIC STEELS; MICROSTRUCTURE; NUCLEAR FUELS; PARTICULATES; PLASTICITY; STRAINS; X-RAY DIFFRACTION
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CARBON COMPOUNDS; COHERENT SCATTERING; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DIFFRACTION; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FERRIMAGNETIC MATERIALS; FUELS; IRON ALLOYS; IRON BASE ALLOYS; IRON COMPOUNDS; LINE DEFECTS; LIQUID METAL COOLED REACTORS; MAGNETIC MATERIALS; MATERIALS; MECHANICAL PROPERTIES; OXYGEN COMPOUNDS; PARTICLES; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SCATTERING; SIMULATION; SODIUM COOLED REACTORS; STEELS; TEST FACILITIES; TEST REACTORS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.