Thermodynamic studies on uranium–molybdenum alloys

Parida, S.C.; Dash, Smruti; Singh, Ziley; Prasad, Rajendra; Venugopal, V.

doi:10.1016/s0022-3697(00)00219-5

Cited by 36 publications

(30 citation statements)

References 15 publications

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“…The mutual solubility of Mo and Al in U extends up to 38 at.%Mo and 3%Al, forming a ternary field, where the cubic U(c) form is easily retained after quenching to room temperature in alloys containing more than %10 at.% Mo, the transformation to the orthorhombic a form occurring for lower Mo contents. These results are in full agreement with previous studies on quenched U-Mo alloys [1,15,16], but are in conflict with the assessed binary Mo-U equilibrium phase diagram. The quenched cU-Mo alloys adopting the cubic c form are then expected to be in a metastable state at room temperature.…”

Section: Resultssupporting

confidence: 86%

Phase relations in the U–Mo–Al ternary system

Noël

Tougait

Dubois

2009

Journal of Nuclear Materials

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Section: Resultssupporting

confidence: 86%

Phase relations in the U–Mo–Al ternary system

Noël

Tougait

Dubois

2009

Journal of Nuclear Materials

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“…13, with error bars representing Fig. 13 are specific-heat-capacity data available from the literature on U-Mo alloys with a similar composition [20][21][22][23][24][25]. The error associated with each sample is relatively small, resulting from the high reproducibility of the measurement for each thermal cycle.…”

Section: Differential Scanning Calorimetrymentioning

confidence: 99%

“…7 [18] and the temperature-dependent thermal conductivity from Eq. 8 [20], which were used to calculate the temperature-dependent thermal diffusivity The model was executed on both LFA samples assuming three different scenarios involving the specific heat capacity: (i) using the average DSC1 data only, (ii) using the average DSC2 data only, and (iii) using the averaged DSC1 and DSC2 data (see Fig. 13).…”

Section: Thermal Conductivitymentioning

confidence: 99%

Development and Validation of Capabilities to Measure Thermal Properties of Layered Monolithic U–Mo Alloy Plate-Type Fuel

et al. 2014

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The uranium-molybdenum (U-Mo) alloy in a monolithic form has been proposed as one fuel design capable of converting some of the world's highest power research reactors from the use of high enriched uranium to low enriched uranium. One aspect of the fuel development and qualification process is to demonstrate appropriate understanding of the thermal-conductivity behavior of the fuel system as a function of temperature and expected irradiation conditions. The purpose of this paper is to verify functionality of equipment installed in hot cells for eventual measurements on irradiated uranium-molybdenum (U-Mo) monolithic fuel specimens, refine procedures to operate the equipment, and validate models to extract the desired thermal properties. The results presented here demonstrate the adequacy of the equipment, procedures, and models that have been developed for this purpose based on measurements conducted on surrogate depleted uranium-molybdenum (DU-Mo) alloy samples containing a Zr diffusion barrier and clad in aluminum alloy 6061 (AA6061). The results are in excellent agreement with thermal property data reported in the literature for similar U-Mo alloys as a function of temperature.

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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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Thermodynamic studies on uranium–molybdenum alloys

Cited by 36 publications

References 15 publications

Phase relations in the U–Mo–Al ternary system

Phase relations in the U–Mo–Al ternary system

Development and Validation of Capabilities to Measure Thermal Properties of Layered Monolithic U–Mo Alloy Plate-Type Fuel

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

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