DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Effect of heat treatment on the microstructure of medium burn-up U-Mo monolithic fuel foils

Journal Article · · Journal of Nuclear Materials
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1];  [2]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]
  1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
  2. Idaho National Laboratory (INL), Idaho Falls, ID (United States). Glenn T. Seaborg Institute

Using scanning electron microscopy (SEM), this study evaluates the microstructure evolution of U-Mo fuel foils made with and without heat treatment at medium burn-up (of approximately 5 x 1021 f/cm3). The impact of annealing treatments on critical microstructural properties of the U-Mo fuel foils, including porosity, grain structure, Mo homogeneity, and fuel interaction with the Zr interlayer, was examined using large area lift outs (LALOs). The heat-treated specimens presented less grain refining at these burnups when compared to the un-heated specimens. Grain refinement was associated with porosities and fission products precipitation. Heat treatment can reduce fuel swelling during irradiation. Chemical inhomogeneity (Mo banding) was found to persist in the un-heated samples but was not present in the heat-treated samples. Thus, heat-treated U-Mo foils allows for more predictable fuel behavior under irradiation with respect to un-heated foils. The U-Mo and Zr interaction layer appears to be thicker and more continuous in the heat-treated sample which has been associated with stronger interface integrity during irradiation, as also observed in previous studies. These observations may indicate an overall improved performance of heat-treated fuel foil in a reactor. Further, the effect of local burn-up on grain size/refinement and porosities in each LALO specimen, sampled from different positions in the fuel foil, was difficult to analyze due to the large standard deviation of these parameters. Finally, evidence of grain refinement by polygonization may be present in these specimens.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
2372615
Report Number(s):
INL/JOU--23-74289-Rev000
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 15 Vol. 593; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (30)

The Effect of Homogenization Heat Treatment on the Texture Evolution in U-10Mo Alloy journal June 2021
Mesoscale Modeling of High Burn-Up Structure Formation and Evolution in UO2 journal October 2019
Formation of the rim structure in high burnup fuel journal September 1997
High burn-up rim structure: evidences that xenon-depletion, pore formation and grain subdivision start at different local burn-ups journal August 1998
Development of very-high-density low-enriched-uranium fuels journal December 1997
The high burn-up structure in nuclear fuel journal December 2010
Mesoscale model for fission-induced recrystallization in U-7Mo alloy journal November 2016
Potential annealing treatments for tailoring the starting microstructure of low-enriched U–Mo dispersion fuels to optimize performance during irradiation journal December 2011
Microstructural characteristics of HIP-bonded monolithic nuclear fuels with a diffusion barrier journal May 2014
Phase transitions during artificial ageing of segregated as-cast U–Mo alloys journal February 2015
Effects of heat treatment on U–Mo fuel foils with a zirconium diffusion barrier journal May 2015
Microstructural evolution of a uranium-10 wt.% molybdenum alloy for nuclear reactor fuels journal October 2015
High burn-up structure of U(Mo) dispersion fuel journal August 2016
Effect of grain morphology on gas bubble swelling in UMo fuels – A 3D microstructure dependent Booth model journal November 2016
Effects of irradiation on the interface between U-Mo and zirconium diffusion barrier journal February 2018
Microstructural characterization of as-fabricated and irradiated U-Mo fuel using SEM/EBSD journal October 2018
Recrystallization kinetics of cold-rolled U-10 wt% Mo journal January 2019
Phase reversion kinetics of thermally decomposed (α + γ′) phases to γ-phase in U – 10 wt% Mo alloy journal March 2020
A critical review of the microstructure of U–Mo fuels journal November 2020
Texture analyses and microstructural evolution in monolithic U-Mo nuclear fuel journal February 2021
U(Mo) grain refinement induced by irradiation with high energy iodine journal May 2021
Impacts of annealing treatment on the microstructure of U-Mo monolithic fuel plates journal June 2022
The complex structural and chemical nature of monolithic U-10Mo fuel and Zr barrier layer journal January 2023
An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup journal March 2023
Possible impacts of Mo chemical banding and second phase impurities on the irradiation behavior of monolithic U-10Mo fuels journal April 2023
Phase transformation of metastable discontinuous precipitation products to equilibrium phases in U10Mo alloys journal November 2018
Fiji: an open-source platform for biological-image analysis journal June 2012
Evaluation of Interface Stresses and Cladding-Cladding Delamination Failures In U-Mo Fuel Plates conference August 2021
RERTR-12 Post-irradiation Examination Summary Report report February 2015
IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL journal April 2014