Engineering topics
Teysseyre, S.
Publications and source records attributed to Teysseyre, S..
Molecular dynamics investigation of threshold displacement energies in CaF 2
Understanding the propagation of radiation damage in a material is paramount to predicting the material damage effects. To date, no current literature has investigated the Threshold Displacement Energy (TDE) of Ca and F atoms in CaF 2 through molecular dynamics and simulated statistical analysis. A set of interatomic potentials between Ca-Ca, F-F, and F-Ca were splined, fully characterizing a pure CaF 2 simulation cell, by using published Born-Mayer-Huggins, standard ZBL, and Coulomb potentials, with a resulting structure within 1% of standard density and published lattice constants. Using this simulation cell, molecular dynamics simulations were performed with LAMMPS using a simulation that randomly generated 500 Ca and F PKA directions for each incremental set of energies, and a simulation in each of the [1 0 0], [1 1 0], and [1 1 1] directions with 500 trials for each incremental energy. MD simulations of radiation damage in CaF 2 are carried out using F and Ca PKAs, with energies ranging from 2 to 200 eV. Probabilistic determinations of the TDE and Threshold Vacancy Energy (TVE) of Ca and F atoms in CaF 2 were performed, as well as examining vacancy, interstitial, and antisite production rates over the range of PKA energies. Many more F atoms were displaced from both PKA species, and though F recombination appears more probable than Ca recombination, F vacancy numbers are higher. In conclusion, the higher number of F vacancies than Ca vacancies suggests F Frenkel pairs dominate CaF 2 damage.
Irradiation Assisted Stress Corrosion Cracking Susceptibility of Alloy X-750 exposed to BWR environments
The effect of irradiation on stress corrosion cracking susceptibility and fracture toughness of alloy X-750 has been investigated. The material has been irradiated at a target temperature of 288°C in the Advanced Test Reactor at Idaho National Laboratory to a fluence of approximately 1.93x1020 n/cm2 (E > 1 MeV). Stress corrosion cracking crack growth rates were determined in both unirradiated and irradiated materials in normal water chemistry and hydrogen water chemistry environments. Although the effect of irradiation on tensile properties and fracture toughness was observed, there was no significant effect of irradiation observed on the propagation rate of stress corrosion cracks.
Small Specimen Crack Initiation Testing Rig
This report presents the design of a small crack initiation testing rig for stress corrosion cracking studies.
Effect of Swelling on Irradiation-Assisted Stress Corrosion Cracking
A highly irradiated stainless steel 304 material irradiated to 27 dpa in the Experimental Breeder Reactor-II was used to investigate the relation between void swelling, grain boundary cohesion and intergranular crack growth rate under solicitation by irradiation assisted stress corrosion cracking. The material selected offered two different swelling amounts (about 2% and 3.7%) in the same material at high dose. The material had been irradiated at the same time, same condition, only the temperature gradient led to different swelling. This material, however, proved to be very resistant to irradiation assisted stress corrosion cracking under pressurized water reactor conditions. The crack growth rates measured were very low with the lowest being obtained with the material exhibiting the most amount of swelling. Micromechanical testing performed with the material exhibiting the higher crack propagation rate demonstrated that the irradiation damages (including void swelling) did not decrease grain boundary cohesion enough to make the grain boundaries the weak points under load solely. Crack path and crack tip analysis showed evidence of material modification ahead of the crack but it is not clear, at this point, if the changes observed were caused by the crack advance or if their presence in front of the crack was causing the low crack growth rate measured.
Surface grain boundary engineering of Alloy 600 for improved resistance to stress corrosion cracking
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