Transient testing of oxide fuels by spark plasma sintering and finite element analysis

In this paper, we report an innovative approach of using spark plasma sintering (SPS) combining with finite element modeling (FEM) to investigate the transient behavior of nuclear fuels. The temperature ramping rates of the SPS with special tooling can be controlled from 5 to 10 degrees C/s up to 500 degrees C/s, mimicking prototypical thermal profiles of the loss-of-coolant-accident (LOCA) and reactivity-induced-accident (RIA) events, respectively. The fresh UO2 pellets with micron grain size are synthesized by SPS. Their fracture and fragmentation behaviors are investigated under transient thermal testing, and temperature-gradient and thermal-stress are calculated by FEM. The micron-sized fresh UO2 displays good thermal shock stability and anti-cracking performance under the LOCA thermal test. Under simulated RIA conditions, the UO2 fuels crack due to the stress induced by the large thermal gradient. The unique capability of SPS with controlled temperature ramping enables a cost-effective approach for rapid screening and high throughput evaluation of nuclear fuels under power transients.

Automated summary

This paper presents an innovative approach using spark plasma sintering (SPS) combined with finite element modeling (FEM) to study the transient behavior of nuclear fuels. The temperature ramping rates of SPS can simulate the thermal profiles of loss-of-coolant-accident (LOCA) and reactivity-induced-accident (RIA) events. Experimental results show that micron-sized fresh UO2 pellets synthesized by SPS exhibit good thermal shock stability and anti-cracking performance under LOCA thermal testing, while cracking occurs under simulated RIA conditions due to the stress induced by large thermal gradients. The unique capability of SPS with controlled temperature ramping enables a cost-effective method for rapid screening and evaluation of nuclear fuels under power transients.