| About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Presentation Title |
Chemical Interaction and Incorporation of Lead with Uranium Nitride Fuels |
| Author(s) |
Andre Broussard, Kun Yang, Jie Lian |
| On-Site Speaker (Planned) |
Andre Broussard |
| Abstract Scope |
Uranium Nitride (UN) has been identified as a prime fuel candidate for Lead Cooled Fast Reactors and as part of a fuel-cladding-coolant combination consisting of Uranium Nitride, Alumina-forming Austenitic Alloys, and Lead (Pb). Here we report the findings of using spark plasma sintering (SPS) to synthesis Pb-doped UN pellets with different amounts (5 and 10 wt%) and different sintering parameters (temperature and pressure). Characterization of pellets is performed via Scanning Electron Microscopy, Energy Dispersive Spectroscopy and X-ray Diffraction. Results of characterization for Pb-doped UN pellet sintered at 1550°C exhibit evaporation of Pb out of the UN pellet while a pellet sintered at 1450°C displays diffusion of Pb into the UN matrix. Ongoing experimentation is being conducted at lower temperatures to verify this result. Further experimentation is planned to incorporate UN pellets into liquid Pb to simulate a reactor environment and determine if U dissolves in liquid Pb. |
| Proceedings Inclusion? |
Undecided |