Global ETD Search
Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.
Results
Showing 1 to 7 of 7 for “"Nuclear Graphite"”.
-
Crack growth resistance in nuclear graphite
… but few studies have focused on polycrystalline graphite. In this study, R-curve behaviour in three commercial grade nuclear graphites, of varying structure and properties, is compared using an optical method, a theoretical compliance method, and, a potential drop (PD) technique to measure crack …
-
Issues of scale in nuclear graphite components
… the effect of specimen size on the strength of nuclear graphites was developed using abstraction techniques and finite element Analysis (FEA). The model was designed to be able to predict the response of nuclear graphites (primarily IM1-24 graphite) using fixed material properties under defined …
-
Porosity Analysis using Machine Learning and Ruthenium Diffusion in Nuclear Graphite Grades.
North Carolina State University Theses Nuclear Engineering.
-
A Study of the Effects of Irradiation and Radiolytic Oxidation of the Pore-Level Structure of Gilsocarbon Nuclear Graphite
The pore-level characterisation of nuclear graphite is critical for predicting reactor safety and for assessing the viability of different grades of graphite material. The majority of studies often focus on the impact of one specific length scale (macroscopic/mesoscopic/ microscopic) but very few …
-
Tritium retention in nuclear graphite, system-level transport, and management strategies for the fluoride-salt-cooled high-temperature reactor
… knowledge of interactions between tritium and nuclear graphite in the molten fluoride salt environment. The total activity, chemical forms, and retention mechanisms for tritium in nuclear graphite were studied through thermal desorption analysis of sample materials from three in-core Flibe salt …
-
A method for in situ SEM fracture studies of brittle materials using the double torsion technique : application to nuclear graphite
This work concerned the design and development of a miniature double torsion (DT) testing rig, for use inside the chamber of a scanning electron microscope, to perform in situ loading studies of brittle materials using the DT fracture mechanics specimen. The in situ performance of the system inside …
-
Managing tritium inventory and release with carbon materials in a fluoride salt-cooled high-temperature reactor
… coolant and solid-uranium fuel composed of graphite and silicon carbide-encapsulated tri-structural isotropic (TRISO) particles. The primary coolant salt is known as flibe (7Li2BeF4), which was chosen for its desirable thermal-hydraulic and neutronic properties. Under irradiation, coolant …