An investigation of structural changes caused by neutron irradiation of a uranium molybdenum alloy

Konobeevskii, S.T.; Pravdyuk, N.F.; Dubrovin, K.P.; Levitskii, B.M.; Panteleev, L. D.; Golianov, V.M.

doi:10.1016/0891-3919(59)90141-1

Cited by 3 publications

(2 citation statements)

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“…Despite the large number of experimental and theoretical studies on the phase diagram, structure, and kinetics of phase transitions in the uranium-molybdenum system performed in the 1950s to 1970s, there is a lot of interest in studying the properties of metal fuels and optimizing the design of fuel structures (for example, dispersed fuel). Although Mo stabilizes the γ-phase of U-Mo alloys, it is still metastable and may decompose into a lamellar two-phase mixture of the orthorhombic α-U and the tetragonal γ -phase U 2 Mo [6][7][8][9]. The microstructure of U-Mo alloy is an inhomogeneous dendrite structure with Mo-rich and Mo-lean regions [6,7,[10][11][12][13].…”

Section: Introductionmentioning

confidence: 99%

Structure and Phase Transition Features of Monoclinic and Tetragonal Phases in U–Mo Alloys

Kolotova

Gordeev

2020

Crystals

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Using molecular dynamics simulations, we studied the structural properties of orthorhombic, monoclinic, and body-centered tetragonal (bct) phases of U–Mo alloys. A sequence of shear transformations between metastable phases takes place upon doping of uranium with molybdenum from pure α -U: orthorhombic α ′ → monoclinic α ″ → bct γ 0 → body-centered cubic (bcc) with doubled lattice constant γ s → bcc γ . The effects of alloy content on the structure of these phases have been investigated. It has been shown that increase in molybdenum concentration leads to an increase in the monoclinic angle and is more similar to the γ 0 -phase. In turn, tetragonal distortion of the γ 0 -phase lattice with displacement of a central atom in the basic cell along the <001> direction makes it more like the α ″ -phase. Both of these effects reduce the necessary shift in atomic positions for the α ″ → γ 0 -phase transition.

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Section: Introductionmentioning

confidence: 99%

Structure and Phase Transition Features of Monoclinic and Tetragonal Phases in U–Mo Alloys

Kolotova

Gordeev

2020

Crystals

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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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X-ray diffraction studies of fission fragment damage in uranium carbide and nitride

Adam

Rogers

1961

Journal of Nuclear Energy. Parts A/B. Reactor Science and Techn

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An investigation of structural changes caused by neutron irradiation of a uranium molybdenum alloy

Cited by 3 publications

References 1 publication

Structure and Phase Transition Features of Monoclinic and Tetragonal Phases in U–Mo Alloys

Structure and Phase Transition Features of Monoclinic and Tetragonal Phases in U–Mo Alloys

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

X-ray diffraction studies of fission fragment damage in uranium carbide and nitride

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