| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
|
| Presentation Title |
Spark Plasma Sintering – Innovative Approaches for High Temperature Creep Testing and Transient Behavior of Nuclear Fuels |
| Author(s) |
Jie Lian |
| On-Site Speaker (Planned) |
Jie Lian |
| Abstract Scope |
Spark plasma sintering (SPS) is an advanced technology in manufacturing nuclear fuels with controlled microstructure and phase behavior. Different fuels are manufactured from conventional UO2, high density silicide and nitride, doped fuels to metallic fuels. SPS also enables high temperature creep testing under vacuum or reducing environments, which is technologically very challenging due to high sensitivity of nuclear fuels to oxidation and pulverization. By controlling power ramping of SPS, rapid heating and cooling varying from several to 15 oC/s can be achieved, allowing transient testing of nuclear fuels under prototypical temperature profiles of loss of coolant events. Ultrafast heating up to 750 oC/s is also demonstrated by controlling tooling of SPS, enabling the testing of transient behavior of nuclear fuels in simulating reactivity-induced events. In this talk, the advancements of using SPS as innovative approaches will be highlighted in testing high temperature creep and transient behaviors of nuclear fuels. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Ceramics, Characterization, Nuclear Materials |