Microstructure and microchemistry changes at U-10Mo fuel/AA6061 cladding interfaces with varying hot isostatic pressing conditions

A Koziol, K Yano, A Schemer-Kohrn, A Soulami… - Journal of Nuclear …, 2023 - Elsevier
Abstract Monolithic uranium-10 wt.% molybdenum (U-10Mo) is a promising high-assay low-
enriched uranium fuel system for nuclear reactors used in research, medical isotope …

A comparison of carbon impurities in pre-and post-melt uranium Part 2: Scanning/Transmission electron microscopy analysis

MJ Olszta, JF Corbey, DD Reilly - Journal of Alloys and Compounds, 2022 - Elsevier
The speciation and morphology of U carbide inclusions in pre-and post-melt U metal have
been explored using high-resolution analytical electron microscopy (AEM). This report …

Compositional partitioning during early stages of oxidation of a uranium-molybdenum alloy

EJ Kautz, SV Lambeets, J Royer, DE Perea, SS Harilal… - Scripta Materialia, 2022 - Elsevier
Compositional partitioning during uranium alloy oxidation was studied via complementary
ex situ-in situ atom probe tomography. Nanoscopic volumes of uranium-22 at …

Microstructural-level fuel performance modeling of U-Mo monolithic fuel

BW Beeler, LK Aagesen Jr, JI Cole, G Hofman… - 2021 - osti.gov
As the physics that governs the microstructural evolution of nuclear fuel span various time
and spatial scales, to fully understand the fuel behavior inevitably involves atomic to …

Influence of processing on secondary phase formation and microstructural evolution at U-10Mo alloy and Zr interlayer interfaces

EJ Kautz, M Song, S Riechers, A Koziol… - Journal of Alloys and …, 2023 - Elsevier
Thermo-mechanical processing of uranium-10 wt% molybdenum (U-10Mo) alloy fuel plates
with a zirconium (Zr) interlayer leads to microstructure changes at fuel/interlayer interfaces …

The role of UC inclusions in the development of fission gas bubble superlattice neutron-irradiated monolithic U-10Mo fuels

C Smith, K Bawane, J Gan, D Keiser, D Salvato… - Journal of Nuclear …, 2023 - Elsevier
Uranium Carbide (UC) inclusions are the most prevalent impurities in Uranium-Molybdenum
(U-Mo) fuel and are considered undesirable because they could potentially affect fuel …

Accelerated fission rate irradiation design, pre-irradiation characterization, and adaptation of conventional PIE methods for U-10Mo and U-17Mo

P Doyle, C Massey, D Richardson… - Frontiers in Nuclear …, 2023 - frontiersin.org
Metallic U alloys have high U density and thermal conductivity and thus have been explored
since the beginning of nuclear power research. Alloys of U with modest amounts of Mo, such …

Effects of uranium metal carbon content on hydriding kinetics and corrosion blister number/area at sub-ambient pressures

A Pital, K Campbell, A Richards, D Kelly - Journal of Radioanalytical and …, 2024 - Springer
Carbon is a common impurity in uranium metal, resulting in a number of uranium–carbon
inclusion phases that contribute to an increase in metal defect density as carbon content …

Possible impacts of Mo chemical banding and second phase impurities on the irradiation behavior of monolithic U-10Mo fuels

CA Smith, JF Jue, T Trowbridge, D Keiser… - Journal of Nuclear …, 2023 - Elsevier
This study investigated the microstructural behavior of both full-size and mini-size monolithic
U-10Mo fuel plates irradiated to high burnup with a focus on the evolution of the second …

Characteristics and Evolution Behavior of Non-metallic Inclusions in a Novel Ni–W–Co Heavy-Density Alloy Manufactured by VIM/VAR

S Yang, P Zhao, S Yang, W Liu, J Li… - Metallurgical and Materials …, 2022 - Springer
Casting and wrought (C&W) metallurgical technology is an effective strategy to fabricate
large-sized heavy-density alloy to reduce costs and improve densification, but inevitably …