Properties of DU–10wt% Mo alloys subjected to various post-rolling heat treatments

Burkes, Douglas E.; Prabhakaran, Ramprashad; Hartmann, Thomas; Jue, Jan‐Fong; Rice, Francine J.

doi:10.1016/j.nucengdes.2010.02.008

Cited by 66 publications

(31 citation statements)

References 10 publications

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“…Distribution of UC and UO 2 inclusions in the U10Mo fuel alloy can cause unexpected physical, mechanical and chemical behavior of the monolithic fuel plate [24][25][26][27]. This manuscript reported some anomalies in chemical interactions between the fuel alloy and Zr diffusion barrier.…”

Section: Microstructural Anomalies and Fuel Fabricationmentioning

confidence: 98%

“…This manuscript reported some anomalies in chemical interactions between the fuel alloy and Zr diffusion barrier. Table 1, in addition to crystallographic details and compositions, lists some of the physical and mechanical properties for the UC, UO 2 and γ (U-10 wt.% Mo) phases [24][25][26][27][28][29][30][31][32][33][34]. During the fabrication of the monolithic fuel plate, large differences in elastic modulus and hardness may cause crack formation within the low-toughness phase.…”

Section: Microstructural Anomalies and Fuel Fabricationmentioning

confidence: 99%

“…According to Nomine et al [25], low solubility of each impurity in uranium causes chemical compound such as the randomly distributed UC phase in U-Mo alloy. Burkes et al [26] examined the mechanical behaviors of U10Mo alloy with carbon, nitrogen and oxygen impurities, and concluded that the failure mode from tensile test was sensitive to impurity content. Hoge [27] also found that carbon content below 250 ppm is desired to prevent reduction of ductility and tensile strength, based on deleterious mechanical effects of carbon on U10Mo alloys.…”

Section: Introductionmentioning

confidence: 99%

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Microstructural anomalies in hot-isostatic pressed U–10 wt.% Mo fuel plates with Zr diffusion barrier

Park

Eriksson

Keiser

et al. 2015

Materials Characterization

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Microstructural anomalies in the co-rolled-and-HIP'ed U-10 wt.% Mo (U10Mo) metallic fuel plate with Zr diffusion barrier assembly were examined as a function of HIP temperature (from 520 to 580°C) and duration (45, 60, 90, 180 and 345 min) by scanning and transmission electron microscopy. The anomalies observed in this study are carbide/oxide inclusions within the U10Mo fuel alloy, and regions of limited interaction between the U10Mo alloy and Zr barrier, frequently associated with carbide/oxide inclusions. In the U10Mo alloy, the cF8, Fm3m (225) UC phase (a = 4.955 Å) and cF12, Fm3m (225) UO 2 phase (a = 5.467 Å) were observed throughout the U10Mo alloy with an approximate volume percent of 0.5 to 1.8. The volume percent of the UC-UO 2 inclusions within the U10Mo alloy did not change as functions of HIP temperature and time. These inclusion phases, located near the surface of the U10Mo alloy, were frequently observed to impede the development of interdiffusion and reaction between the U10Mo alloy and Zr diffusion barrier. The regions of limited interaction between the U10Mo and Zr barrier decreased with an increase in HIP temperature, however no noticeable trend was observed with an increase in HIP duration at constant temperature of 560°C.

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Section: Microstructural Anomalies and Fuel Fabricationmentioning

confidence: 98%

Section: Microstructural Anomalies and Fuel Fabricationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Microstructural anomalies in hot-isostatic pressed U–10 wt.% Mo fuel plates with Zr diffusion barrier

Park

Eriksson

Keiser

et al. 2015

Materials Characterization

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“…Mo has high solubility in -U that allows for fuel customization, and the alloy satisfies the fissile-U densities required by the RERTR program. Extensive studies and characterization of UMo alloys have been carried out to develop an understanding of the phase equilibria , kinetics [45][46][47][48][49][50][51][52], mechanical properties [53][54][55][56][57], thermodynamics [58][59][60][61][62] and irradiation behavior [63][64][65][66][67][68][69][70][71][72][73] of this system. In early studies, Pfeil [22], Saller et al [23][24][25], Ivanov et al [29,34], Carrera et al [26] and Dwight et al [27] detailed the -U ( -U + -U 2 Mo) decomposition that takes place below 573°C.…”

Section: Introductionmentioning

confidence: 99%

Results of U-xMo (x=7, 10, 12 wt.%) Alloy versus Al-6061 Cladding Diffusion Couple Experiments Performed at 500, 550 and 600 Degrees C

Perez¹,

Keiser²,

Sohn³

2013

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The Reduced Enrichment for Research and Test Reactors (RERTR) program has been developing low-enrichment fuel systems encased in Al-6061 for use in research and test reactors. U-Mo alloys in contact with Al and Al alloys can undergo diffusional interactions that can result in the development of interdiffusion zones with complex fine-grained microstructures composed of multiple phases. A monolithic fuel currently being developed by the RERTR program has local regions where the U-Mo fuel plate is in contact with the Al-6061 cladding and, as a result, the program finds information about interdiffusion zone development at high temperatures of interest. In this study, the microstructural development of diffusion couples consisting of U-7wt.%Mo, U-10wt.%Mo, and U-12wt.%Mo vs. Al-6061 (or 6061 aluminum) cladding, annealed at 500, 550, 600°C for 1, 5, 20, 24, or 132 hours, was analyzed by backscatter electron microscopy and x-ray energy dispersive spectroscopy on a scanning electron microscope. Concentration profiles were determined by standardized wavelength dispersive spectroscopy and standardless x-ray energy dispersive spectroscopy. The results of this work shows that the presence of surface layers at the U-Mo/Al-6061 interface can dramatically impact the overall interdiffusion behavior in terms of rate of interaction and uniformity of the developed interdiffusion zones. It further reveals that relatively uniform interaction layers with higher Si concentrations can develop in U-Mo/Al-6061 couples annealed at shorter times and that longer times at temperature result in the development of more non-uniform interaction layers with more areas that are enriched in Al. At longer annealing times and relatively high temperatures, UMo/Al-6061 couples can exhibit more interaction compared to U-Mo/pure Al couples. The minor alloying constituents in Al-6061 cladding can result in the development of many complex phases in the interaction layer of U-Mo/Al-6061 cladding couples, and some phases in the interdiffusion zones of U-Mo/Al-6061 cladding couples are likely similar to those observed for U-Mo/pure Al couples.

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“…Molybdenum has a substantial solubility in U, up to ≈ 35% [5]. The research showed that the (γ)U-Mo alloys can be promising candidates for LEU fuels, since they meet core criteria for fuel qualification [11]; e.g., they have a higher stability under irradiation and are more resistant to swelling (than α-U alloys) [12,13]. Beside of their greater fissile load, their manufacturing is easier [14].…”

mentioning

confidence: 99%

γ-U phase in U-Pt system retained to low temperatures by means of rapid cooling

Kim-Ngan

Paukov

Tarasenko

et al. 2016

Journal of Nuclear Materials

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Properties of DU–10wt% Mo alloys subjected to various post-rolling heat treatments

Cited by 66 publications

References 10 publications

Microstructural anomalies in hot-isostatic pressed U–10 wt.% Mo fuel plates with Zr diffusion barrier

Microstructural anomalies in hot-isostatic pressed U–10 wt.% Mo fuel plates with Zr diffusion barrier

Results of U-xMo (x=7, 10, 12 wt.%) Alloy versus Al-6061 Cladding Diffusion Couple Experiments Performed at 500, 550 and 600 Degrees C

γ-U phase in U-Pt system retained to low temperatures by means of rapid cooling

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