Irradiation behavior of the interaction product of U-Mo fuel particle dispersion in an Al matrix.
- Nuclear Engineering Division
Irradiation performance of U-Mo fuel particles dispersed in Al matrix is stable in terms of fuel swelling and is suitable for the conversion of research and test reactors from highly enriched uranium (HEU) to low enriched uranium (LEU). However, tests of the fuel at high temperatures and high burnups revealed obstacles caused by the interaction layers forming between the fuel particle and matrix. In some cases, fission gas filled pores grow and interconnect in the interdiffusion layer resulting in fuel plate failure. Postirradiation observations are made to examine the behavior of the interdiffusion layers. The interdiffusion layers show a fluid-like behavior characteristic of amorphous materials. In the amorphous interdiffusion layers, fission gas diffusivity is high and the material viscosity is low so that the fission gas pores readily form and grow. Based on the observations, a pore formation mechanism is proposed and potential remedies to suppress the pore growth are also introduced.
- Research Organization:
- Argonne National Laboratory (ANL)
- Sponsoring Organization:
- NA
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1048029
- Report Number(s):
- ANL/NE/JA-73331
- Journal Information:
- Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 1-3 Vol. 425; ISSN 0022-3115; ISSN JNUMAM
- Country of Publication:
- United States
- Language:
- ENGLISH
Similar Records
Microstructural characterization of an irradiated RERTR-6 U-7Mo/AA4043 alloy dispersion fuel plate specimen blister-tested to a final temperature of 500°C
Effects of Irradiation on the Microstructure of U-7Mo Dispersion Fuel with Al-2Si Matrix