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- Accident tolerant fuel (1)
- Ceramic coating on clad (1)
- Ceramic film (1)
- Defect-free channel formation (1)
- Dislocation random walk (1)
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- Flow localization (1)
- Helium (1)
- Iron (1)
- Irradiation embrittlement (1)
- Irradiation hardening (1)
- MD Simulation (1)
- Missing Pellet Surface (1)
- Nuclear engineering (1)
- Nuclear fuel (1)
- Pellet Cladding Interaction (1)
- Thermal Desorption Spectrometry (TDS) (1)
- Thermal Desorption Spectrum (TDS) Measurement (1)
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Articles 1 - 4 of 4
Full-Text Articles in Engineering Science and Materials
Modeling Of Dislocation Channel Formation And Evolution In Irradiated Metals, Peter James Doyle
Modeling Of Dislocation Channel Formation And Evolution In Irradiated Metals, Peter James Doyle
Masters Theses
Defect-free dislocation channel formation has been reported to promote plastic instability during tensile testing via localized plastic flow, leading to a distinct loss of ductility and strain hardening in many low-temperature irradiated materials. In order to study the underlying mechanisms governing dislocation channel width and formation, the channel formation process is modeled via a simple stochastic dislocation-jog process dependent upon grain size, defect cluster density, and defect size. Dislocations traverse a field of defect clusters and jog stochastically upon defect interaction, forming channels of low defect-density. Based upon prior molecular dynamics (MD) simulations and in-situ experimental transmission electron microscopy (TEM) …
Development And Application Of 3-D Fuel Performance Modeling To Assess Missing Pellet Surface Influence On Pellet Clad Interaction And Clad Failure, Nathan Allen Capps
Development And Application Of 3-D Fuel Performance Modeling To Assess Missing Pellet Surface Influence On Pellet Clad Interaction And Clad Failure, Nathan Allen Capps
Doctoral Dissertations
In the late 1970s PCI related failures caused the implementation of startup ramp restrictions. These ramp restrictions where intended to reduce the stresses caused by pellet cladding contact. These ramp restrictions had a significant impact on Westinghouse fueled PWRs, reducing PCI related failure until 2003. Through investigation into these fuel rod failures lead to the conclusion that missing pellet surfaces (MPS) were the root cause of the failures. MPS are local geometric defects in nuclear fuel pellets that result from pellet mishandling or the manufacturing process. The presence of MPS defects can cause stress concentrations in the clad of sufficient …
Modeling And Experimental Investigation On The Influence Of Radiation Defects On Helium Behavior In Bcc Iron, Zuya Huang
Modeling And Experimental Investigation On The Influence Of Radiation Defects On Helium Behavior In Bcc Iron, Zuya Huang
Masters Theses
Fe-based alloys are important structural materials for both fission and fusion energy. For fusion applications, the challenges of radiation-induced changes in microstructure, properties and performance is further challenged by the concomitant production of helium from (n, alpha) nuclear reactions and fusion reactions. Due to the lack of a volumetric, high flux 14-MeV neutron source, studying these phenomena require the use of computational materials modeling and novel experimental methods. In this thesis, molecular dynamics (MD) simulations was used to investigate the synergistic interactions of helium with prismatic dislocation loops characteristic of those observed in neutron irradiated iron to determine how the …
Impact Of Fuel Rod Coatings On Reactor Performance And Safety, Ian Robert Stewart
Impact Of Fuel Rod Coatings On Reactor Performance And Safety, Ian Robert Stewart
Masters Theses
This study evaluates the use of a ceramic coating on the Zr-alloy cladding within a PWR using four ceramic compounds of 5 and 10 micron thicknesses: ZrO2, TiAlN, Ti2AlC, and Ti3AlC2. The film’s impact is assessed for variation on: reactivity, fuel cycle length, maximum temperature, film’s roughness, and transient conditions. The reactivity is analyzed using the following methods: change in the multiplication factor (k) each film introduces to the system using the ABH method, and Monte Carlo software (MCNP). Both methods are in good agreement, yielding less than half a percent change from a reference, no-film fuel pin. In order …