| People | Locations | Statistics |
|---|---|---|
| Naji, M. |
| |
| Motta, Antonella |
| |
| Aletan, Dirar |
| |
| Mohamed, Tarek |
| |
| Ertürk, Emre |
| |
| Taccardi, Nicola |
| |
| Kononenko, Denys |
| |
| Petrov, R. H. | Madrid |
|
| Alshaaer, Mazen | Brussels |
|
| Bih, L. |
| |
| Casati, R. |
| |
| Muller, Hermance |
| |
| Kočí, Jan | Prague |
|
| Šuljagić, Marija |
| |
| Kalteremidou, Kalliopi-Artemi | Brussels |
|
| Azam, Siraj |
| |
| Ospanova, Alyiya |
| |
| Blanpain, Bart |
| |
| Ali, M. A. |
| |
| Popa, V. |
| |
| Rančić, M. |
| |
| Ollier, Nadège |
| |
| Azevedo, Nuno Monteiro |
| |
| Landes, Michael |
| |
| Rignanese, Gian-Marco |
|
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
| Organizations | Location | People |
|---|
report
Design and Thermal Analysis for Irradiation of Silicon Carbide Joint Specimens in the High Flux Isotope Reactor
Abstract
This report provides a summary of the irradiation vehicle design and thermal analysis of SiC joint specimens planned for irradiation in the flux trap of the High Flux Isotope Reactor (HFIR). Two different capsule designs will be used to accommodate the two different specimen geometries: a small torsion joint specimen geometry to measure mechanical and thermal properties, and a tube and end plug joint representative cladding geometry to demonstrate strength and hermeticity retention. The capsule designs, with target temperatures of 350° and 750°C, will accommodate either sixteen torsion joint specimens or one tube end plug joint specimen. Three joint variations will be studied in each capsule design: a hybrid SiC (preceramic polymer with chemical vapor deposition (CVD) SiC), a transient eutectic phase (TEP) process, and an oxide process.