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Journal articles on the topic 'Uranium-molybdenum alloy'

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Author: Grafiati

Published: 10 December 2022

Last updated: 28 January 2023

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1

Visser, A. E., R. A. Pierce, and J. E. Laurinat. "Purification of Uranium from a Uranium/Molybdenum Alloy." Separation Science and Technology 43, no. 9-10 (July 18, 2008): 2775–85. http://dx.doi.org/10.1080/01496390802121701.

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2

Chmela, T., and P. Krupička. "The oxidation kinetics of depleted uranium and its low-alloy molybdenum alloys in moist air." Koroze a ochrana materialu 63, no. 3 (November 1, 2019): 100–104. http://dx.doi.org/10.2478/kom-2019-0013.

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Abstract The oxidation kinetics of depleted uranium and its low-alloy molybdenum alloys (U-2wt.%Mo, U-5wt.%Mo) were measured in a moist air (75% relative humidity) at 60 and 75 ° C. Coefficients of reaction rate equations were determined for linear oxidation kinetics. In the oxidation of depleted uranium at 75 ° C, a change in reaction kinetics from linear to exponential behaviour was observed after about 2500 hours.

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3

Meyer, M. K., G. L. Hofman, S. L. Hayes, C. R. Clark, T. C. Wiencek, J. L. Snelgrove, R. V. Strain, and K. H. Kim. "Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel." Journal of Nuclear Materials 304, no. 2-3 (August 2002): 221–36. http://dx.doi.org/10.1016/s0022-3115(02)00850-4.

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4

Orlov, V. K., V. M. Teplinskaya, and N. T. Chebotarev. "Decomposition of a metastable solid solution in uranium-molybdenum alloy." Atomic Energy 88, no. 1 (January 2000): 42–47. http://dx.doi.org/10.1007/bf02673318.

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5

Adamska, A. M., R. Springell, and T. B. Scott. "Characterization of poly- and single-crystal uranium–molybdenum alloy thin films." Thin Solid Films 550 (January 2014): 319–25. http://dx.doi.org/10.1016/j.tsf.2013.11.087.

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6

Kautz, Elizabeth J., Sten V. Lambeets, Jacqueline Royer, Daniel E. Perea, Sivanandan S. Harilal, and Arun Devaraj. "Compositional partitioning during early stages of oxidation of a uranium-molybdenum alloy." Scripta Materialia 212 (April 2022): 114528. http://dx.doi.org/10.1016/j.scriptamat.2022.114528.

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7

Camarano, D. M., F. A. Mansur, A. M. M. Santos, W. B. Ferraz, and T. A. Pedrosa. "Effects of heat treatments on the thermal diffusivity of Uranium-Molybdenum alloy." Journal of Physics: Conference Series 733 (July 2016): 012014. http://dx.doi.org/10.1088/1742-6596/733/1/012014.

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8

Naymushin, Artem G., Yuri B. Chertkov, Vasily V. Kurganov, Ivan I. Lebedev, Svetlana A. Mongush, and Natalya V. Daneikina. "Feasibility Study of Using New Fuel Composition in IRT-T Research Reactor." Advanced Materials Research 1084 (January 2015): 306–8. http://dx.doi.org/10.4028/www.scientific.net/amr.1084.306.

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The results of simulation of IRT-T reactor conversion from highly enriched fuel to new perspective low enriched fuel based on uranium-molybdenum alloy are given. Main characteristics of reacting core with the use of highly enriched and low enriched fuel are calculated. It is shown that impact of using new materials in fuel composition remains neutronic and thermal hydraulic characteristics of the core at an acceptable level.

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9

Karpyuk, L. A., A. M. Savchenko, Yu V. Konovalov, G. A. Kulakov, S. V. Maranchak, S. A. Ershov, E. V. Maynikov, et al. "Features of the behavior of the dispersion fuel METMET under irradiation." Voprosy Materialovedeniya, no. 3(111) (November 1, 2022): 148–55. http://dx.doi.org/10.22349/1994-6716-2022-111-3-148-155.

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The paper considers the behavior under irradiation of the METMET fuel composition, which consists of particles of uranium-molybdenum alloy in a matrix of zirconium alloys. Post-reactor investigations confirmed the satisfactory performance of pilot fuel elements irradiated in the MIR reactor to a burnup of 61 MW day/kgU under significant thermal loads. The structural stability of the fuel under irradiation, good compatibility of the fuel rod components with each other could be noted. Fuel rods with METMET fuel composition have good prospects for use in reactors of floating nuclear power units and low-capacity nuclear plants, as well as a tolerant fuel.

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10

Kolotova, Lada, and Ilia Gordeev. "Structure and Phase Transition Features of Monoclinic and Tetragonal Phases in U–Mo Alloys." Crystals 10, no. 6 (June 16, 2020): 515. http://dx.doi.org/10.3390/cryst10060515.

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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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11

Clarke, A. J., K. D. Clarke, R. J. McCabe, C. T. Necker, P. A. Papin, R. D. Field, A. M. Kelly, et al. "Microstructural evolution of a uranium-10 wt.% molybdenum alloy for nuclear reactor fuels." Journal of Nuclear Materials 465 (October 2015): 784–92. http://dx.doi.org/10.1016/j.jnucmat.2015.07.004.

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12

Gattu, Vineeth Kumar, and William L. Ebert. "Multiphase Alloy Nuclear Waste Forms Developed for Pyrochemical U-10Mo Scrap Recovery Waste Streams." ECS Meeting Abstracts MA2022-02, no. 12 (October 9, 2022): 772. http://dx.doi.org/10.1149/ma2022-0212772mtgabs.

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The US High Performance Research Reactor (USHPRR) Conversion program is developing an Al-clad Zr-bonded U-10Mo nuclear fuel foil to enable the conversion of research reactors to high-assay low-enriched uranium (HALEU) alloy fuel. Fabrication scrap from the fuel manufacturing will be electrorefined to recover the HALEU, which will generate waste streams consisting of Zr, Mo, and residual U retained in the stainless steel anode basket used in the electrorefiner. Four alloys were formulated with different relative amounts of Zr, Mo, and 316L-SS to represent the expected range of waste compositions. Laboratory-scale ingots were made and metallurgically characterized to assess differences in the microstructures and distributions of the surrogate waste metals. Different amounts of the same dominant phases with similar compositions were formed in most materials: a γ-austenite based matrix, two ZrFe2 intermetallic phases that could host residual uranium, an FeCrMo sigma (σ) intermetallic phase, a chi (χ) phase, and a secondary austenite (γ2) phase. Electrochemical tests were conducted to compare the corrosion behaviors in acidic and alkaline brine solutions for a range of simulated environmental redox conditions. Corrosion of the Mo-rich γ and γ2 solid solutions and the σ and χ intermetallic phases occurred. The multiphase alloy waste form formulated with the lowest molybdenum and highest zirconium contents showed the highest corrosion resistance and has sufficient amounts of ZrFe2 to immobilize trace amounts of residual uranium in the waste stream. The alloy formulation strategy and testing approach will be presented with key results. Work conducted at Argonne National Laboratory is operated for the U.S. Department of Energy, Office of Science under contact DE-AC02-06CH11357.

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13

Rest, J., G. L. Hofman, and Yeon Soo Kim. "Analysis of intergranular fission-gas bubble-size distributions in irradiated uranium–molybdenum alloy fuel." Journal of Nuclear Materials 385, no. 3 (April 2009): 563–71. http://dx.doi.org/10.1016/j.jnucmat.2009.01.001.

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14

Belyaev, Dmitry, Alexey Aleksandrov, Yuri Zuyev, Eugene Kozlov, Igor Svyatov, and Catherine Levi. "Structure of U-Zr-Mo alloy shell after explosive loading." EPJ Web of Conferences 183 (2018): 03025. http://dx.doi.org/10.1051/epjconf/201818303025.

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This presentation describes investigation of a thick-wall spherical shell 48 mm in diameter from the alloy of uranium with molybdenum and zirconium, which survived after high-intensity explosive loading. Investigation was performed in the meridional section of the shell to obtain qualitative data on hardness and microhardness, metallurgical inclusions, damage, and also material microstructure. Structural changes are observed to widely present in the shell material. The localized damage observed both at R ≈ 12-14 mm and R ≈ 16-18 mm are the first and second converged spalls, respectively. What is more, in the southern sector the first spall was recompacted with the remelting of a large region of the material in the adjacent layers (region with the enhanced hardness for the first spall). Cracks of the second spall in the northern sector were also recompacted almost completely.

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15

Ouyang, Wenhong, Wensheng Lai, Jiahao Li, Jianbo Liu, and Baixin Liu. "Atomic Simulations of U-Mo under Irradiation: A New Angular Dependent Potential." Metals 11, no. 7 (June 24, 2021): 1018. http://dx.doi.org/10.3390/met11071018.

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Uranium-Molybdenum alloy has been a promising option in the production of metallic nuclear fuels, where the introduction of Molybdenum enhances mechanical properties, corrosion resistance, and dimensional stability of fuel components. Meanwhile, few potential options for molecular dynamics simulations of U and its alloys have been reported due to the difficulty in the description of the directional effects within atomic interactions, mainly induced by itinerant f-electron behaviors. In the present study, a new angular dependent potential formalism proposed by the author’s group has been further applied to the description of the U-Mo systems, which has achieved a moderately well reproduction of macroscopic properties such as lattice constants and elastic constants of reference phases. Moreover, the potential has been further improved to more accurately describe the threshold displacement energy surface at intermediate and short atomic distances. Simulations of primary radiation damage in solid solutions of the U-Mo system have also been carried out and an uplift in the residual defect population has been observed when the Mo content decreases to around 5 wt.%, which corroborates the negative role of local Mo depletion in mitigation of irradiation damage and consequent swelling behavior.

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16

Kolotova, L. N., S. V. Starikov, and V. D. Ozrin. "Atomistic Simulation of the Fission-Fragment-Induced Formation of Defects in a Uranium–Molybdenum Alloy." Journal of Experimental and Theoretical Physics 129, no. 1 (July 2019): 59–65. http://dx.doi.org/10.1134/s1063776119060128.

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17

Huang, Ke, Dennis D. Keiser, and Yongho Sohn. "Interdiffusion, Intrinsic Diffusion, Atomic Mobility, and Vacancy Wind Effect in γ(bcc) Uranium-Molybdenum Alloy." Metallurgical and Materials Transactions A 44, no. 2 (October 2, 2012): 738–46. http://dx.doi.org/10.1007/s11661-012-1425-9.

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18

Bachhav, Mukesh, Brandon Miller, Jian Gan, Dennis Keiser, Ann Leenaers, S. Van den Berghe, and Mitchell K. Meyer. "Microstructural Changes and Chemical Analysis of Fission Products in Irradiated Uranium-7 wt.% Molybdenum Metallic Fuel Using Atom Probe Tomography." Applied Sciences 11, no. 15 (July 27, 2021): 6905. http://dx.doi.org/10.3390/app11156905.

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Understanding the microstructural and phase changes occurring during irradiation and their impact on metallic fuel behavior is integral to research and development of nuclear fuel programs. This paper reports systematic analysis of as-fabricated and irradiated low-enriched U-Mo (uranium-molybdenum metal alloy) fuel using atom probe tomography (APT). This study is carried out on U-7 wt.% Mo fuel particles coated with a ZrN layer contained within an Al matrix during irradiation. The dispersion fuel plates from which the fuel samples were extracted are irradiated at Belgian Nuclear Research Centre (SCK CEN) with burn-up of 52% and 66% in the framework of the SELENIUM (Surface Engineering of Low ENrIched Uranium-Molybdenum) project. The APT studies on U-Mo particles from as-fabricated fuel plates enriched to 19.8% revealed predominantly γ-phase U-Mo, along with a network of the cell boundary decorated with α-U, γ’-U2Mo, and UC precipitates along the grain boundaries. The corresponding APT characterization of irradiated fuel samples showed formation of fission gas bubbles enriched with solid fission products. The intermediate burnup sample showed a uniform distribution of the typical bubble superlattice with a radius of 2 nm arranged in a regular lattice, while the high burnup sample showed a non-uniform distribution of bubbles in grain-refined regions. There was no evidence of remnant α-U, γ’-U2Mo, and UC phases in the irradiated U-7 wt.% Mo samples.

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19

Mushtaq, A. "Specifications and qualification of uranium/aluminum alloy plate target for the production of fission molybdenum-99." Nuclear Engineering and Design 241, no. 1 (January 2011): 163–67. http://dx.doi.org/10.1016/j.nucengdes.2010.11.003.

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20

Bacon, Simon R., Martin Brierley, Mark A. Baker, and John F. Watts. "Oxidation of a depleted uranium‐5 wt% molybdenum (U‐5Mo) alloy in UHV by AES and XPS." Surface and Interface Analysis 51, no. 8 (May 27, 2019): 849–56. http://dx.doi.org/10.1002/sia.6659.

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21

Muenze, Rudolf, Gerd Juergen Beyer, Richard Ross, Gerhard Wagner, Dieter Novotny, Erik Franke, Mustansar Jehangir, Shahid Pervez, and Ahmad Mushtaq. "The Fission-Based 99Mo Production Process ROMOL-99 and Its Application to PINSTECH Islamabad." Science and Technology of Nuclear Installations 2013 (2013): 1–9. http://dx.doi.org/10.1155/2013/932546.

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An innovative process for fission based99Mo production has been developed under Isotope Technologies Dresden (ITD) GmbH (former Hans Wälischmiller GmbH (HWM), Branch Office Dresden), and its functionality has been tested and proved at the Pakistan Institute of Nuclear Science and Technology (PINSTECH), Islamabad. Targets made from uranium aluminum alloy clad with aluminum were irradiated in the core of Pakistan Research Reactor-1 (PARR-1). In the mean time more than 50 batches of fission molybdenum-99 (99Mo) have been produced meeting the international purity/pharmacopoeia specifications using this ROMOL-99 process. The process is based on alkaline dissolution of the neutron irradiated targets in presence of NaNO3, chemically extracting the99Mo from various fission products and purifying the product by column chromatography. This ROMOL-99 process will be described in some detail.

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22

Boyd, G. A. C., J. Harding, P. A. Bleasdale, K. Dunn, and G. Turner. "THE EFFECT OF QUENCHING RATE ON THE TEMPERATURE AND STRAIN-RATE SENSITIVITY OF URANIUM 2w/o MOLYBDENUM ALLOY." Le Journal de Physique Colloques 46, no. C5 (August 1985): C5–487—C5–494. http://dx.doi.org/10.1051/jphyscol:1985561.

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23

Bol'shakov, A. P., A. S. Girin, S. A. Novikov, V. A. Pushkov, and V. A. Sinitsyn. "Strain diagrams for uranium and its alloy with molybdenum in dynamic uniaxial compression and tension and at elevated temperatures." Journal of Applied Mechanics and Technical Physics 40, no. 6 (November 1999): 1173–79. http://dx.doi.org/10.1007/bf02469192.

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24

Shchepin, Andrey S., Andrey M. Koshcheev, Ivan V. Kuznetsov, Maya Yu Kalenova, and Irina M. Melnikova. "SNF processing electrochemical operations: liquid-metal and salt medium purification." Nuclear Energy and Technology 8, no. 1 (March 18, 2022): 55–61. http://dx.doi.org/10.3897/nucet.8.82620.

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The paper investigates the process of regeneration of a liquid metal medium used in the pyroelectrochemical reprocessing of spent mixed uranium-plutonium nitride fuel produced by a fast neutron reactor. The investigation concerns the interaction of liquid cadmium with sludge formed during the anodic dissolution of ceramic nitride pellets in a 3LiCl-2KCl melt medium as well as the possibility of its purification by filtration from individual metal fission products. Anode sludge is represented by fission products of the platinum group, zirconium, molybdenum and technetium. It was determined by scanning electron microscopy that the metal product is composed of several intergrowth phases. It was found that upon contact of a polymetallic alloy simulating anode sludge with a melt, the liquid metal phase is saturated to 0.025 wt% of Pd, 0.01 wt% of Rh for 50 hours at 500 °C, while zirconium forms an insoluble dispersed intermetallic compound ZrCd3. Powders of molybdenum and technetium, which are not wetted with cadmium, can be completely removed using a filter mesh of plain weaving of the P-200 type. It is also possible to remove zirconium from anodic cadmium by filtration. The filtration efficiency of ruthenium and palladium powders did not exceed 54.3 and 13.1 wt%, respectively, due to partial dissolution and thinning of particles, which will lead to saturation of the liquid metal phase and the need to purify it by alternative methods.

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25

Boyd, G. A. C., J. Harding, P. A. Bleasdale, K. Dunn, and G. I. Turner. "The effect of temperature and strain rate on the tensile strength of a fast-gas-cooled uranium-2 wt% molybdenum alloy." Journal of Nuclear Materials 132, no. 2 (June 1985): 181–91. http://dx.doi.org/10.1016/0022-3115(85)90413-1.

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26

Parida, S. C., S. Dash, Z. Singh, R. Prasad, and V. Venugopal. "Thermodynamic studies on uranium–molybdenum alloys." Journal of Physics and Chemistry of Solids 62, no. 3 (March 2001): 585–97. http://dx.doi.org/10.1016/s0022-3697(00)00219-5.

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27

Iasir, A. Rafi M., and Karl D. Hammond. "Xenon mobility in γ-uranium and uranium–molybdenum alloys." Journal of Applied Physics 131, no. 2 (January 14, 2022): 025105. http://dx.doi.org/10.1063/5.0059157.

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28

Mukherjee, S., S. K. Sharma, V. Sinha, and P. K. Pujari. "Positron annihilation spectroscopy of Uranium Molybdenum alloys." Journal of Physics: Conference Series 618 (June 15, 2015): 012019. http://dx.doi.org/10.1088/1742-6596/618/1/012019.

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29

de Oliveira, Fábio Branco Vaz, and Humberto Gracher Riella. "Hydrogen Absorption-Desorption and Gamma-UMo Nuclear Fuel Powder Production." Materials Science Forum 591-593 (August 2008): 201–5. http://dx.doi.org/10.4028/www.scientific.net/msf.591-593.201.

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Gamma uranium-molybdenum alloys has been considered as the fuel phase in plate type fuel elements for MTR reactors due to its performance under irradiation and metallurgical processing. To its usage as dispersion phase in aluminum matrix, a necessary step is the conversion of the as cast structure into powder, and the technique considered at IPEN / CNEN - Brazil was HDH (hydration-dehydration). This work has the aim to study the hydrogen incorporation by gamma-UMo alloys with 8% weight molybdenum. The samples were thermally treated under constant flow of hydrogen, for temperatures varying from 500oC up to 600oC and times of 1 to 4 hours. Some of the curves relating mass incorporation and time for the above temperatures were obtained, and the results related to its microstructures and ease of fragmentation.

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30

Pasqualini, Enrique E. "Alternative processes of comminution and colamination of uranium molybdenum alloys." Progress in Nuclear Energy 75 (August 2014): 92–104. http://dx.doi.org/10.1016/j.pnucene.2014.04.002.

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31

Tkach, I., N. T. H. Kim-Ngan, S. Mašková, M. Dzevenko, L. Havela, A. Warren, C. Stitt, and T. Scott. "Characterization of cubic γ-phase uranium molybdenum alloys synthesized by ultrafast cooling." Journal of Alloys and Compounds 534 (September 2012): 101–9. http://dx.doi.org/10.1016/j.jallcom.2012.04.028.

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32

Sinha, V. P., G. J. Prasad, P. V. Hegde, R. Keswani, C. B. Basak, S. Pal, and G. P. Mishra. "Development, preparation and characterization of uranium molybdenum alloys for dispersion fuel application." Journal of Alloys and Compounds 473, no. 1-2 (April 2009): 238–44. http://dx.doi.org/10.1016/j.jallcom.2008.05.061.

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33

Sinha, V. P., P. V. Hegde, G. J. Prasad, G. K. Dey, and H. S. Kamath. "Effect of molybdenum addition on metastability of cubic γ-uranium." Journal of Alloys and Compounds 491, no. 1-2 (February 2010): 753–60. http://dx.doi.org/10.1016/j.jallcom.2009.11.060.

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34

Zhong, Yu-Ke, Kui Liu, Ya-Lan Liu, Yue-Xiang Lu, Tai-Qi Yin, Lin Wang, Zhi-fang Chai, and Wei-Qun Shi. "Preparation of γ-Uranium-Molybdenum Alloys by Electrochemical Reduction of Solid Oxides in LiCl Molten Salt." Journal of The Electrochemical Society 166, no. 8 (2019): D276—D282. http://dx.doi.org/10.1149/2.0201908jes.

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35

Ignat’ev, V. V., A. I. Surenkov, I. P. Gnidoi, V. S. Uglov, and S. A. Konakov. "Experimental Investigation of Tellurium Corrosion of Nickel-Molybdenum Alloys in Molten Lithium-, Beryllium-, and Uranium-Fluoride Salts." Atomic Energy 120, no. 6 (September 30, 2016): 397–402. http://dx.doi.org/10.1007/s10512-016-0148-1.

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36

Barluzzi, Luciano, Nadir Jori, Tianyi He, Thayalan Rajeshkumar, Rosario Scopelliti, Laurent Maron, Paul Oyala, Theodor Agapie, and Marinella Mazzanti. "Heterometallic uranium/molybdenum nitride synthesis via partial N-atom transfer." Chemical Communications 58, no. 29 (2022): 4655–58. http://dx.doi.org/10.1039/d2cc00473a.

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Reaction of a Mo(ii) terminal nitride with U(iii) generates the first example of a transition metal capped uranium nitride. The nitride is triply bonded to U(v) and singly bonded to Mo(0) with a U–Mo interaction and reacts with CO to yield cyanate.

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37

Ayres, Alexander J., Markus Zegke, Joseph P. A. Ostrowski, Floriana Tuna, Eric J. L. McInnes, Ashley J. Wooles, and Stephen T. Liddle. "Actinide-transition metal bonding in heterobimetallic uranium– and thorium–molybdenum paddlewheel complexes." Chemical Communications 54, no. 96 (2018): 13515–18. http://dx.doi.org/10.1039/c8cc05268a.

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38

Säubert, Steffen, Rainer Jungwirth, Tobias Zweifel, Michael Hofmann, Markus Hoelzel, and Winfried Petry. "Neutron and hard X-ray diffraction studies of the isothermal transformation kinetics in the research reactor fuel candidate U–8 wt%Mo." Journal of Applied Crystallography 49, no. 3 (May 16, 2016): 923–33. http://dx.doi.org/10.1107/s1600576716005744.

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Exposing uranium–molybdenum alloys (UMo) retained in the γ phase to elevated temperatures leads to transformation reactions during which the γ-UMo phase decomposes into the thermal equilibrium phases,i.e.U2Mo and α-U. Since α-U is not suitable for a nuclear fuel exposed to high burn-up, it is necessary to retain the γ-UMo phase during the production process of the fuel elements for modern high-performance research reactors. The present work deals with the isothermal transformation kinetics in U–8 wt%Mo alloys for temperatures between 673 and 798 K and annealing durations of up to 48 h. Annealed samples were examined at room temperature using either X-ray or neutron diffraction to determine the phase composition after thermal treatment, andin situannealing studies disclosed the onset of phase decomposition. While for temperatures of 698 and 673 K the start of decomposition is delayed, for higher temperatures the first signs of transformation are already observable within 3 h of annealing. The typical C-shaped curves in a time–temperature–transformation (TTT) diagram for both the start and the end of phase decomposition could be determined in the observed temperature regime. Therefore, a revised TTT diagram for U–8 wt%Mo between 673 and 798 K and annealing durations of up to 48 h is proposed.

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39

Summers, Robert, and David Weaver. "Phosphorus Retention of a Permeable Reactive Barrier Surpassed by an Unvegetated Artificial Pond." Environment and Natural Resources Research 11, no. 1 (December 11, 2021): 25. http://dx.doi.org/10.5539/enrr.v11n1p25.

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An artificial pond bisected by a phosphorus (P) retentive permeable reactive barrier (PRB) alongside Forrest Highway, Coolup, Western Australia was designed to remove P from farmland runoff. The pond bed was made of subsoil and road construction materials likely to have a relatively high P sorption capacity, and there was no vegetation in the bed of the pond. Flow through the pond was intercepted by the PRB, constructed from a mixture of sand, coarse crushed limestone, and bauxite residue (with 10% phospho-gypsum). The effectiveness of P removal and the impact of the PRB was measured by comparing the concentration of contaminants immediately either side of the PRB with established standards, and against background levels in runoff from surrounding farmland. Using coarse limestone to increase flow through the PRB failed where permeability was insufficient to avoid overtopping of the PRB and the wall had to be lowered to allow by-pass and avoid collapse. The PRB was effective in removing total P (TP); however, the influent TP concentration was low (mean 0.19 mg L -1 ) because most P entering from farmland was retained in the shallow pond upstream of the PRB. Despite this, TP removal by the PRB was 53% (2009–2012). Occasionally, in spring when the pond was stagnant and anaerobic, P was released from the PRB. This minor P release coincided with a minor release of iron, consistent with anaerobic conditions found in the PRB. Although not designed to do so, the shallow pond upstream of the PRB reduced the TP concentration from farmland by 85% (mean 1.26 mg L -1 down to 0.19 mg L -1 ), mainly by reducing filterable reactive P concentration. Some elements (arsenic, cobalt, conductivity, fluoride, manganese, molybdenum, pH, selenium, uranium and vanadium) were increased by flow through the PRB, but were low relative to surrounding waters and environmental standards

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40

Suryaman, Ganisa Kurniati, Muhammad Waziz Wildan, Supardjo Supardjo, and Yatno Dwi Agus Susanto. "PRODUCTION OF URANIUM-MOLYBDENUM ALLOY AS A CANDIDATE FOR NUCLEAR RESEARCH REACTOR FUEL." Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir 24, no. 3 (December 28, 2018). http://dx.doi.org/10.17146/urania.2018.24.3.4685.

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PRODUCTION OF URANIUM−MOLYBDENUM ALLOY AS A CANDIDATE FOR NUCLEAR RESEARCH REACTOR FUEL. Research and development on high density uranium for nuclear research reactor fuel is still in progress. Uranium-molybdenum alloy is one of the strongest candidates of nuclear research reactor fuel material. The properties and characteristics of U-Mo alloy is of important consideration for the selction of the fabrication techniques for the production of the fuel. In this work, uranium-molybdenum (U-Mo) alloys with varied molybdenum content have been produced succesfully by arc melting technique. The molybdenum content variations were 7 %wt, 8 %wt, 9 %wt and 10 %wt Mo. The melting process was done 5 times to achieve homogenization. Metallographic micrograph shows the presence of dendritic structure. XRD examination result affirms the presence of 2 phases of γ-U phase and d-U2Mo phase. Microhardness Vickers test shows higher hardness value for Uranium-molybdenum alloy with higher molybdenum content.Keywords: U−Mo alloy, research reactor, fuel.

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Nielsen, Guilherme Fernandes, Nathanael Wagner Sales Morais, and Nelson Batista de Lima. "Crystallographic texture of hot rolled uranium-molybdenum alloys." Brazilian Journal of Radiation Sciences 8, no. 3A (February 9, 2021). http://dx.doi.org/10.15392/bjrs.v8i3a.1406.

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The uranium molybdenum (U-Mo) alloys have potential to be used as low enriched uranium nuclear fuel in research, test and power nuclear reactors. U-Mo alloy with composition between 7 and 10 wt% molybdenum shows excellent body centered cubic phase (γ phase) stabilization and presents a good nuclear fuel testing performance. Hot rolling is commonly utilized to produce parallel fuel plate where it promotes the cladding and the fuel alloy bonding. The mechanical deformation generates crystallographic preferential orientation, the texture, which influences the material properties. This work studied the texture evolution in hot rolled U-Mo alloys. The U7.4Mo and U9.5Mo alloys were melted in a vacuum induction furnace, homogenized at 1000°C for 5 h and then hot rolled at 650°C in three height reductions: 50, 65 and 80%. The crystalline phases and the texture were evaluated by X-ray diffraction (XRD). The as-cast and processed alloys microstructures were characterized by optical and electronic microscopies. The as-cast, homogenized and deformed alloys have γ phase. It was found microstructural differences between the U7.4Mo and U9.5Mo alloys. The homogenized treatment showed effective for microsegregation reduction and were not observed substantial grain size increasing. The deformed uranium molybdenum alloys presented α, γ, θ texture fibers. The intensity of these texture fibers changes with deformation step.

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Wang, Chao, Zhijie Xu, Deborah Fagan, David P. Field, Curt Lavender, and Vineet V. Joshi. "Quantifying and Qualifying Alloys Based on Level of Homogenization: A U-10Mo Alloy Case Study." Journal of Engineering Materials and Technology 142, no. 1 (October 9, 2019). http://dx.doi.org/10.1115/1.4044891.

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Abstract Homogenization heat treatment is performed to attain uniformity in microstructure which is helpful to achieve the desired workability and microstructure in final products and, eventually, to gain predictive and consistent performance. Fabrication of low-enriched uranium alloys with 10 wt% molybdenum (U-10Mo) fuel plates involves multiple thermomechanical processing steps. It is well known that the molybdenum homogeneity in the final formed product affects the performance in the nuclear reactor. To ensure uniform homogenization, a statistical method is proposed to quantify and characterize the molybdenum concentration variation in U-10Mo fuel plates by analyzing the molybdenum concentration measurement data from scanning electron microscopy energy dispersive spectroscopy line-scan. Statistical tolerance intervals (TI) are employed to determine the qualification of the U-10Mo fuel plate. We formulate an argument for the minimum number of independent samples to define fuel plate qualification if no molybdenum measurement data are available in advance and demonstrate that the given TI requirements can be equivalently reduced to a sample variance criterion in this application. The outcome of the statistical analysis can be used to optimize casting design and eventually increase productivity and reduce fabrication costs. The statistical strategy developed in this paper can be implemented for other applications especially in the field of material manufacturing to assess qualification requirements and monitor and improve the process design.

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Rest, J., G. L. Hofman, I. I. Konovalov, and A. A. Maslov. "Effect of Formation and Growth of Dislocation Loops and Cavities on Low-Temperature Swelling of Irradiated Uranium-Molybdenum Alloys." MRS Proceedings 540 (1998). http://dx.doi.org/10.1557/proc-540-609.

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AbstractScanning electron photomicrographs of U–10 wt.% Mo irradiated at low temperature in the Advanced Test Reactor (ATR) to about 40 at.% burnup show the presence of cavities. We have used a rate-theory-based model to investigate the nucleation and growth of cavities during low-temperature irradiation of uranium-molybdenum alloys in the presence of irradiation-induced interstitial-loop formation and growth. Our calculations indicate that the swelling mechanism in the U–10 wt.% Mo alloy at low irradiation temperatures is fission-gas driven. The calculations also indicate that the observed bubbles must be associated with a subgrain structure. Calculated bubble-size-distributions are compared with irradiation data.

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Borts, B. V., I. N. Laptev, A. A. Parkhomenko, A. F. Vanzha, I. A. Vorobjev, and Yu A. Marchenko. "ANALYSES OF STRUCTURE PHASE STABILITY OF U-Mo TARGET OF THE NEUTRON SOURCE." Problems of Atomic Science and Technology, January 30, 2020, 161–66. http://dx.doi.org/10.46813/2020-125-161.

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The paper presents analyses of structure phase stability of fuel materials by means of phase diagrams of martensite transformation method, proposed earlier for the system of “iron-carbon-vacancy”. It was shown that role of molybdenum in stabilization of uranium gamma-structure under irradiation is to hinder of the phase to phase transformations of martensite type. The role of point defects and electron structure in the process of homogenization of alloy structure in the process of irradiation was studied.

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Fu, Yucheng, William E. Frazier, Kyoo Sil Choi, Lei Li, Zhijie Xu, Vineet V. Joshi, and Ayoub Soulami. "Prediction of grain structure after thermomechanical processing of U-10Mo alloy using sensitivity analysis and machine learning surrogate model." Scientific Reports 12, no. 1 (June 28, 2022). http://dx.doi.org/10.1038/s41598-022-14731-8.

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AbstractHot rolling and annealing are critical intermediate steps for controlling microstructures and thickness variations when fabricating uranium alloyed with 10% molybdenum (U-10Mo), which is highly relevant to worldwide nuclear non-proliferation efforts. This work proposes a machine-learning surrogate model combined with sensitivity analysis to identify and predict U-10Mo microstructure development during thermomechanical processing. Over 200 simulations were collected using physics-based microstructure models covering a wide range of thermomechanical processing routes and initial alloy grain features. Based on the sensitivity analysis, we determined that an increase in rolling reduction percentage at each processing pass has the strongest effect in reducing the grain size. Multi-pass rolling and annealing can significantly improve recrystallization regardless of the reduction percentage. With a volume fraction below 2%, uranium carbide particles were found to have marginal effects on the average grain size and distribution. The proposed stratified stacking ensemble surrogate predicts the U-10Mo grain size with a mean square error four times smaller than a standard single deep neural network. At the same time, with a significant speedup (1000×) compared to the physics-based model, the machine learning surrogate shows good potential for U-10Mo fabrication process optimization.

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Hirschhorn, Jacob, Floyd Hilty, Michael R. Tonks, and Jhonathan Rosales. "Review and Preliminary Investigation into Fuel Loss from Cermets Composed of Uranium Nitride and a Molybdenum-Tungsten Alloy for Nuclear Thermal Propulsion Using Mesoscale Simulations." JOM, September 21, 2021. http://dx.doi.org/10.1007/s11837-021-04873-x.

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Rest, J., and G. L. Hofman. "Irradiation-Induced Recrystallization of Cellular Dislocation Networks in Uranium-Molybdenum Alloys." MRS Proceedings 650 (2000). http://dx.doi.org/10.1557/proc-650-r1.7.

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ABSTRACTWe developed a rate-theory-based model to investigate the nucleation and growth of interstitial loops and cavities during low-temperature in-reactor irradiation of uranium-molybdenum alloys. Consolidation of the dislocation structure takes into account the generation of forest dislocations and capture of interstitial dislocation loops. The theoretical description includes stress-induced glide of dislocation loops and accumulation of dislocations on cell walls. The loops accumulate and ultimately evolve into a low-energy cellular dislocation structure. Calculations indicate that nanometer-size bubbles are associated with the walls of the cellular dislocation structure. The accumulation of interstitial loops within the cells and of dislocations on the cell walls leads to increasing values for the rotation (misfit) of the cell wall into a subgrain boundary and a change in the lattice parameter as a function of dose. Subsequently, increasing values for the stored energy in the material are shown to be sufficient for the material to undergo recrystallization. Results of the calculations are compared with SEM photomicrographs of irradiated U- 10Mo, as well as with data from irradiated UO2.

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"Effect of Concentration of Mo on the Mechanical behavior of γ UMo: an Atomistic Study." Petroleum and Chemical Industry International 4, no. 3 (December 30, 2021). http://dx.doi.org/10.33140/pcii.04.03.05.

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We performed molecular dynamics simulation on nanoindentation ofγ phase Uranium Molybdenum alloys using spherical indenter. A ternary potential developed for UMoXe was utilized. We calculated the updated values for hardness and reduced elastic modulus at different concentrations of Mo. The whole process of deformation and dislocation analysis was visualized using OVITO. We found an increase in deformation withincreasein stress while dislocations are not found anyhow induced defects have been distributed throughout the simulation cell randomly. The increase in concentration affected the hardness and reduced elastic modulus significantly. This study provides insights into the structure and mechanical characteristics of γ UMo under deformation.

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