| People | Locations | Statistics |
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| Naji, M. |
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| Motta, Antonella |
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| Aletan, Dirar |
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| Mohamed, Tarek |
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| Ertürk, Emre |
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| Taccardi, Nicola |
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| Kononenko, Denys |
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| Petrov, R. H. | Madrid |
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| Alshaaer, Mazen | Brussels |
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| Bih, L. |
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| Casati, R. |
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| Muller, Hermance |
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| Kočí, Jan | Prague |
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| Šuljagić, Marija |
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| Kalteremidou, Kalliopi-Artemi | Brussels |
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| Azam, Siraj |
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| Ospanova, Alyiya |
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| Blanpain, Bart |
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| Ali, M. A. |
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| Popa, V. |
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| Rančić, M. |
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| Ollier, Nadège |
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| Azevedo, Nuno Monteiro |
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| Landes, Michael |
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| Rignanese, Gian-Marco |
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Linton, Kory D.
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (10/10 displayed)
- 2018In-cell Re-fabrication and Loss-of-coolant Accident (LOCA) Testing of High Burnup Commercial Spent Fuel
- 2018Assembly and Delivery of Rabbit Capsules for Irradiation of Reinforced Radiation Resistant SiC-SiC Composites in the High Flux Isotope Reactor
- 2018Design and Thermal Analysis for Irradiation of Silicon Carbide Joint Specimens in the High Flux Isotope Reactor
- 2018Report on Design and Failure Limits of SiC/SiC and FeCrAl ATF Cladding Concepts under RIA
- 2018Completion of the Irradiation of Silicon Carbide Cladding Tube Specimens in the High Flux Isotope Reactor
- 2018Design and Thermal Analysis for Irradiation of Tensile Specimens from Wrought, Powder Metallurgy, and Additive Processed Alloys in the HFIR
- 2017Transition Fracture Toughness Characterization of Eurofer 97 Steel using Pre-Cracked Miniature Multi-notch Bend Bar Specimens
- 2017Radiation Induced Segregation at Low Angle Grain Boundaries in Steels: NSUF 2017 Milestone Report
- 2017Irradiation of Wrought FeCrAl Tubes in the High Flux Isotope Reactor
- 2017In-pile Hydrothermal Corrosion Evaluation of Coated SiC Ceramics and Composites
Places of action
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report
Assembly and Delivery of Rabbit Capsules for Irradiation of Reinforced Radiation Resistant SiC-SiC Composites in the High Flux Isotope Reactor
Abstract
The development of reinforced radiation resistant composites presents a critical challenge for in-vessel component application in advanced high temperature reactors. In its pursuit of this, Physical Optics Corporation (POC) is interested in developing a silicon carbide (SiC)-based ceramic matrix composite (CMC) with improved thermal conductivity in a high neutron radiation environment. The US Department of Energy (DOE) is supporting research efforts to develop Advanced Reactor Technology. Ultimately, the results of this project will determine the viability of using SiC matrix composites in hot structures in advanced high temperature reactors. The first objective of this project is to irradiate torsion and bend bar specimens in the High Flux Isotope Reactor (HFIR) and develop an initial data set to evaluate the evolution of composite mechanical strength, dimensional changes, and thermal conductivity. This report briefly describes the irradiation experiment design concepts, summarizes the irradiation test matrix, and reports on the successful delivery of three rabbit capsules to the HFIR. Rabbits of both torsion and bend bar configurations have been assembled, welded, evaluated, and delivered to the HFIR along with a complete quality assurance fabrication package.