Philip D. Edmondson
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View article: Analysis of a segmentation approach to breeder blanket design and the utilisation of FLiBe as a novel neutron reflector
Analysis of a segmentation approach to breeder blanket design and the utilisation of FLiBe as a novel neutron reflector Open
Tritium production in a fusion reactor is essential for a deuterium-tritium burning plasma source, and designing a lithium-containing breeder blanket is crucial for a closed fuel cycle in an electricity-to-grid power plant. Tritium is a ra…
View article: Characterization of the Irradiation Effects in Nuclear Graphite
Characterization of the Irradiation Effects in Nuclear Graphite Open
Graphite serves as the neutron moderator of British Gas-Cooled Reactors and is a candidate material for the Generation IV of nuclear power stations. The neutron irradiation affects the crystalline structure of graphite; this damage results…
View article: Nanoprecipitates to Enhance Radiation Tolerance in High-Entropy Alloys
Nanoprecipitates to Enhance Radiation Tolerance in High-Entropy Alloys Open
The growth of advanced energy technologies for power generation is enabled by the design, development, and integration of structural materials that can withstand extreme environments, such as high temperatures, radiation damage, and corros…
View article: SEM and TEM data of nuclear graphite and glassy carbon microstructures
SEM and TEM data of nuclear graphite and glassy carbon microstructures Open
Micrographs of multiple nuclear graphite grades were captured using scanning electron microscopy (SEM) and transmission electron microscopy (TEM), complementing the data contained in the related manuscript, "A multi-technique image library…
View article: Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review
Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review Open
Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS) steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. The performance of these steels will deteriorate during servic…
View article: Probing the Damage Recovery Mechanism in Irradiated Stainless Steels Using In-Situ Microcantilever Bending Test
Probing the Damage Recovery Mechanism in Irradiated Stainless Steels Using In-Situ Microcantilever Bending Test Open
Single crystalline microcantilevers are fabricated from the base metal and heat-affected zone (HAZ) of a laser welded, neutron irradiated austenitic stainless steel, for scanning electron microscope (SEM) in-situ bending. In the HAZ, canti…