TEM Characterization of High Burn-up Microstructure of U-7Mo Alloy
As an essential part of global nuclear non-proliferation effort, the RERTR program is developing low enriched U-Mo fuels (< 20% U-235) for use in research and test reactors that currently employ highly enriched uranium fuels. One type of fuel being developed is a dispersion fuel plate comprised of U-7Mo particles dispersed in Al alloy matrix. Recent TEM characterizations of the ATR irradiated U-7Mo dispersion fuel plates include the samples with a local fission densities of 4.5, 5.2, 5.6 and 6.3 E+21 fissions/cm3 and irradiation temperatures of 101-136?C. The development of the irradiated microstructure of the U-7Mo fuel particles consists of fission gas bubble superlattice, large gas bubbles, solid fission product precipitates and their association to the large gas bubbles, grain subdivision to tens or hundreds of nanometer size, collapse of bubble superlattice, and amorphisation. This presentation will describe the observed microstructures specifically focusing on the U-7Mo fuel particles. The impact of the observed microstructure on the fuel performance and the comparison of the relevant features with that of the high burn-up UO2 fuels will be discussed.
- Research Organization:
- Idaho National Laboratory (INL)
- Sponsoring Organization:
- DOE - NA
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1148997
- Report Number(s):
- INL/CON-13-30688
- 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