Progress in postirradiation examination and analysis of low-enriched U-Mo research reactor fuels.
Conference
·
OSTI ID:947955
High-density dispersion fuel experiment, RERTR-4, was removed from the Advanced Test Reactor (ATR) after reaching a peak U-235 burnup of {approx}80% and is presently undergoing postirradiation examination at the ANL Alpha-Gamma Hot Cell Facility. This test consists of 32 mini fuel plates of which 27 were fabricated with nominally 6 and 8 g cm-3 atomized and machined uranium alloy powders containing 6.5 wt% to 10 wt% molybdenum. In addition, two miniplates containing solid U-10wt%Mo foils. The results of the postirradiation examination and analysis of RERTR-4 in conjunction with data from a companion test performed to 50% burnup, RERTR-5, are presented.
- Research Organization:
- Argonne National Laboratory (ANL)
- Sponsoring Organization:
- NNSA
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 947955
- Report Number(s):
- ANL/TD/CP-109789
- Country of Publication:
- United States
- Language:
- ENGLISH
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