Engineering topics
Edmondson, P. D.
Publications and source records attributed to Edmondson, P. D..
Solid breeder material crystal structure evolution due to Li burn up–Loss of crystal stability
Solid breeder materials for fusion power plants are subjected to extreme conditions of radiation damage, high temperature and designed component burn-up. Here, the loss of lattice stability of Li 2 TiO 3 due to Li burn-up was investigated using first principles-based approaches to aid evaluation of upper limit of component lifetime. The lattice stability is analyzed using calculated phonon dispersion in the Li 2 TiO 3 supercell, while Li burn-up is modeled by the introduction of Li-vacancies. It has been determined that the studied ceramic can be structurally stable up to ~40% of Li atoms burn-up. At 50% burn-up, the negative frequency branch in the phonon dispersion spectrum appears indicating the loss of lattice dynamical stability. Moreover, the structure obtained by introduction of unstable frozen phonons with minima energy amplitude also results in a phonon dispersion with negative branches in the structure obtained. Therefore, the system completely loses stability when approximately half of Li atoms are consumed.
Phase instabilities in austenitic steels during particle bombardment at high and low dose rates
Disruption of phase stability by energetic particle bombardment is a major challenge in designing advanced radiation-tolerant alloys and ion beam processing of nanocomposites. Particularly, ballistic dissolution susceptibility of different solute nanocluster species in alloys is poorly understood. Here, low dose rate neutron irradiations were conducted on a Fe-Cr-Ni based austenitic steel in the BOR-60 reactor (9.4 × 10 -7 dpa/s, 318 °C) followed by accelerated dose rate ion irradiations at multiple temperatures ( 10 -3 dpa/s, 380 – 420 °C). Using atom probe tomography, the stability of radiation-enhanced Cu-rich and radiation-induced Ni-Si-Mn-rich nanoclusters was evaluated. During neutron irradiation, Cu-rich clusters nucleated with their core concentrations progressively increasing with dose, while Ni-Si-Mn-rich clusters formed and evolved into G-phase precipitates. Ion irradiations dramatically altered the nanoclusters. Cu-rich clusters were ballistically dissolved, but Ni-Si-Mn-rich clusters remained stable and coarsened with dose at 400 and 420 °C, highlighting that different nanocluster species in a single microstructure can have innately distinct ballistic dissolution susceptibilities. Solute-specific recoil rates were incorporated into the Heinig precipitate stability model, which shows that in addition to radiation-enhanced diffusion, recovery from ballistic dissolution depends on solute concentration gradient near cluster interfaces. Finally, the combined experimental-modeling study quantified the critical temperatures and damage rates where ballistic dissolution dominates for each cluster species.
Corrosion resistance of functionally graded TiN/Ti coatings for proton exchange membrane fuel cells
Bipolar Plates (BPP) are important components of proton exchange membrane fuel cell (PEMFC) stacks. In the development of innovative fuel cell designs, it is advantageous to use aluminum for these applications, however, this material lacks the necessary corrosion resistance. Since the performance of PEMFC stacks depends on BPP properties, in particular, corrosion resistance, depositing titanium nitride (TiN) thin films onto aluminum substrates may improve their efficiency and durability. Present work focuses on improving corrosion resistance and hydrophobicity of TiN/Ti by using N graded films deposited onto aluminum substrates (AA-1100) by grid-assisted magnetron sputtering (GAMS). Electrochemical impedance spectroscopy (EIS) with potentiodynamic and potentiostatic polarization are used to investigate the performance of the substrate/film system at room temperature and 70 oC, thus simulating a prototypic PEMFC electrolyte environment. Electrochemical test results showed that graded TiN films improved corrosion resistance when compared with both the homogeneous films and the AA1100 uncoated substrate. Furthermore, contact angle results reveal improved hydrophobicity for both homogeneous and graded TiN coatings when compared with the AA1100 substrate.
Response of unalloyed tungsten to mixed spectrum neutrons
Neutron irradiation in mixed spectrum reactors is an effective approach to investigate the synergistic effects of solid transmutations and atomic displacement damage in tungsten. In this article the findings and interpretations from a large-scale tungsten irradiation campaign conducted using the High Flux Isotope Reactor of Oak Ridge National Laboratory are summarized. The response of originally-unalloyed tungsten to mixed spectrum neutron irradiation is characterized by enormous hardening, degradation of modulus of toughness eventually leading to embrittlement, and decreased thermal conductivity. These property changes may be attributed primarily to production, segregation, and precipitation of rhenium and osmium and assisted by displacement damage. The stages describing the evolution of the microstructural development and property changes with the neutron dose and the accompanying accumulation of transmutation products are proposed.
Beam current effect as a potential challenge in SEM-EBSD in situ tensile testing
Highlights: • In situ SEM-EBSD tensile tests were conducted using 304L steels with 8 and 10.4% Ni. • KAM and GROD evolution, twinning, and phase instability were investigated. • Phase transformation in 8% Ni-steel was sensitive to the electron beam current. In situ mechanical tensile tests coupled with electron backscatter diffraction (EBSD) analysis were conducted using specimens of two 304L steels with ~8 and 10.4% Ni content, respectively. Twinning was observed in steel with 10.4% Ni content, whereas steel with 8% Ni content demonstrated martensitic transformation. Testing showed that the kinetics of martensitic transformation in steel with 8% Ni content was influenced by the electron beam current used during EBSD scans. Continuous scanning using 32 nA nominal beam current led to suppression of the phase instability in the near-surface layer, but acceptable comparable-to-the-bulk results were obtained using 8 nA beam current. The exact mechanism of the beam current role is unclear, but it appears to be neutral regarding Kernel Average Misorientation behavior and deformation-induced twinning.
Phase stability of single phase Al0.12CrNiFeCo high entropy alloy upon irradiation
Not Available
Using complimentary microscopy methods to examine Ni-Mn-Si-precipitates in highly-irradiated reactor pressure vessel steels
Nano-scale Ni-Mn-Si-rich precipitates formed in a reactor pressure vessel steel under high neutron fluence have been characterized using highly complimentary atom probe tomography (APT) and scanning transmission electron microscopy with energy dispersive spectroscopy (STEM-EDS) combined with STEM-EDS modeling. Using these techniques in a synergistic manner to overcome the well-known trajectory aberrations in APT data, the average upper limit Fe concentration within the precipitates was found to be ~6 at.%. Using this knowledge, accurate compositions of the precipitates was determined and it was found that the spread of precipitate compositions was large, but mostly centered around the Γ2-and G-phases. The use of STEM-EDS also allowed for larger areas to be examined, and segregation of minor solutes was observed to occur on grain boundaries, along with Ni-Mn-Si-rich precipitates that were smaller in size than those in the matrix. Solute segregation at the grain boundaries is proposed to occur through a radiation induced segregation or radiation enhanced diffusion mechanism due to the presence of a denuded zone about the grain boundary. It is also proposed that the reduced precipitate size at the grain boundaries is due to the structure of the grain boundary. The lack of Ni-Mn-Si precipitates observed in larger Mo-rich precipitates is also discussed, and the absence of the minor solutes required to form the Ni-Mn-Si precipitates results in the lack of nucleation. This is in contrast to cementite phases in which Ni-Mn-Si precipitates have been seen to be formed. It was also determined through this work that the exclusion of all the Fe ions during atom probe analysis is a reasonable approximation.
Electron microscopy analysis of high burnup commercial fuel
Modern electron microscopy analysis can provide detailed insight into the microstructure and chemistry of high burnup UO{sub 2} fuel. This more complete understanding of fuel evolution and performance in reactor can provide critical insight necessary to validate fuel performance models and optimize reactor operations. Preliminary results from the investigation of a polished cross-section of high burnup UO{sub 2} fuel (seven cycles) from the H.B. Robinson pressurized water reactor will be discussed. The analysis focuses on scanning electron microscopy (SEM) of the complete cross-section, while scanning transmission electron microscopy (S/TEM) was performed on targeted features identified by SEM where specimens were fabricated by traditional focused ion beam lift-out techniques. Analysis of the complete cross-section allowed for investigation of the microstructural variations from centerline to fuel/clad interface, pellet/pellet interface, and cladding. Secondary electron imaging and backscatter electron imaging was performed to identify variations in the distribution of fission product secondary phases and bubbles/voids. The analysis of the pellet/pellet interface is a unique feature of this sample where initial analysis shows segregation of fission product phases at the pellet/pellet interface and also indicates an interface microstructure lacking of bubbles and voids. X-ray spectrum imaging was performed by both SEM and STEM techniques to identify the composition of the secondary phases present in the fuel. Multivariate statistical analysis (MVSA) of the X-ray spectrum images has been applied to improve the sensitivity of the analysis and highlight minor variations in the fuel chemistry and secondary phases comprised of fission product as well as the distribution of sub-surface Xe gas bubbles in the high burnup structure. The results presented demonstrate the level of microstructural understanding that is attainable with a combination of SEM techniques along with S/TEM techniques.
Dependencies of α' Embrittlement in Neutron-Irradiated Model Fe-Cr-Al Alloys
Fe-Cr-Al alloys are currently under consideration as accident tolerant fuel cladding materials due to their superior performance in high temperature steam environments when compared to Zr-based alloys. These alloys have also shown promise for other nuclear reactor and power production applications due to their excellent high-temperature oxidation and corrosion resistance. However, like other high-Cr ferritic Fe-based alloys, these alloys are prone to radiation-induced hardening and embrittlement due to the precipitation of a Cr-rich-α' phase under typical LWR operating conditions. Additionally, the kinetics of this phase separation have been shown to be accelerated by irradiation. Current research efforts are focused on developing an ideal candidate Fe-Cr-Al alloy composition and microstructure that retains its exceptional environmental compatibility while maintaining adequate mechanical performance over the duration of its operational lifetime. The current work investigates both the composition and dose dependencies of α' phase precipitation, as it can be the primary contributor to radiation-induced hardening and embrittlement in these alloys. The comprehensive analysis of phase stability in irradiated Fe-Cr-Al alloys provided by this work is a key step forward in assessing the radiation tolerance and overall viability of these materials for accident tolerant fuel cladding applications. Additional work is underway to assess radiation-induced dislocation loop formation in these specimens and correlate the morphologies of both the dislocation loop and α' precipitate morphologies to the results of mechanical testing campaigns in order to fully develop the structure-property relationships for this class of alloys. Completion of this work will allow for a comprehensive evaluation of the suitability of Fe-Cr-Al alloys for nuclear applications and result in the recommendation of an optimized candidate alloy ideally suited for LWR environments. (authors)
An in situ transmission electron microscopy study of the ion irradiation induced amorphisation of silicon by He and Xe
We used transmission electron microscopy with in situ ion irradiation to examine the ion-beam-induced amorphisation of crystalline silicon under irradiation with light (He) and heavy (Xe) ions at room temperature. Analysis of the electron diffraction data reveal the heterogeneous amorphisation mechanism to be dominant in both cases. Moreover, for the differences in the amorphisation curves are discussed in terms of intra-cascade dynamic recovery, and the role of electronic and nuclear loss mechanisms.
Editorial
The development of nuclear materials for the next generation of reactor technology, e.g. GenIV and fusion, is at a critical juncture, with an increasing body of research into the long-term effects of radiation damage on materials being examined. As it is hopefully evident from the papers in this journal issue, there are many pertinent and challenging topics for research in this exciting and challenging area of research, driving forward the development of new materials and the next generation of nuclear reactor technologies.