Uranium-molybdenum alloys in reactor construction

Калашников, В. В.; Titova, V. V.; Sergeev, G. I.; Samoilov, A. G.

doi:10.1007/bf02276888

Cited by 19 publications

(4 citation statements)

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“…(Sinha, Prasad et al 2009) (Keywords: fission reactor fuel preparation, fission research reactors, ingots, materials preparation, molybdenum alloys, powder metallurgy, uranium alloys, X-ray diffraction) "Uranium-Molybdenum Alloys in Reactor Construction" See summary above. (V. V. Kalashnikov 1959) "Development status of metallic dispersion and non-oxide advanced and alternative fuels for power and research reactors" IAEA report, IAEA-TECHDOC-1374 See Summary above. (Y. Arai 2003)…”

Section: U-mo (8)mentioning

confidence: 99%

Corrosion report for the U-Mo fuel concept

Henager

Bennett

Doherty

et al. 2014

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The Fuel Cycle Research and Development (FCRD) program of the Office of Nuclear Energy (NE) has implemented a program to develop a Uranium-Molybdenum (U-Mo) metal fuel for Light Water Reactors (LWR)s. Uranium-Molybdenum fuel has the potential to provide superior performance based on its thermo-physical properties, which includes high thermal conductivity for less stored heat energy. With sufficient development, it may be able to provide the Light Water industry with a melt-resistant accident tolerant fuel with improved safety response. However, the corrosion of this fuel in reactor water environments needs to be further explored and optimized by additional alloying. The Pacific Northwest National Laboratory has been tasked with performing ex-reactor corrosion testing to characterize the performance of U-Mo fuel. This report documents the results of the effort to characterize and develop the U-Mo metal fuel concept for LWRs with regard to corrosion testing. The results of a simple screening test in buffered water at 30˚C using surface alloyed U-10Mo is documented and discussed. The screening test was used to guide the selection of several potential alloy improvements that were found and are recommended for further testing in autoclaves to simulate PWR water conditions more closely.

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Section: U-mo (8)mentioning

confidence: 99%

Corrosion report for the U-Mo fuel concept

Henager

Bennett

Doherty

et al. 2014

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“…Among other common alloying elements like zirconium and niobium, molybdenum (Mo) has high solubility in γ-U and γ-U-Mo has shown relatively moderate swelling behavior under irradiation, with other benefits including high thermal conductivity and low thermal expansion. [2][3][4] Among other challenges for further utilization in nuclear industry, irradiation swelling in U-Mo alloy poses threat on the stability of configuration dimension and mechanical properties of fuel under service environment, where the evolution of fission gas bubble (FGB) plays a critical role. Efforts have been paid to build reliable prediction of swelling behavior of U-Mo fuel, [5][6][7] among which a correlation between volume swelling and fission density, that is, ANL correlation, [3] has been put forward.…”

Section: Introductionmentioning

confidence: 99%

Atomic simulations of primary irradiation damage in U–Mo–Xe system

Ouyang¹,

Li²,

Wang³

et al. 2023

Chinese Phys. B

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To shed a light on Xe bubble nucleation in U-Mo fuel from the view of primary irradiation damage, a reported U-Mo-Xe potential under the framework of embedded atom method has been modified within the range of short and intermediate atomic distance. The modified potential can better describe the interactions between energetic particles, and can accurately reproduce the threshold displacement energy surface calculated by the first principle method. Then, molecular dynamics simulations of primary irradiation damage in U-Mo-Xe system have been conducted under different contents. The raise of Xe concentration brings about a remarkable promotion in residual defect quantity and generates bubbles in more over-pressured state, which suggests an acceleration of irradiation damage under the accumulation of the fission gas. Meanwhile, the addition of Mo considerably reduces the residual defect count and hinders irradiation-induced Xe diffusion especially at high contents of Xe, corroborating the importance of high Mo content in mitigation of irradiation damage and swelling behavior in U-Mo fuel. In particular, the variation of irradiation damage with respect to contents suggests a necessity of taking into account the influence of local components on defect evolution in mesoscale simulations.

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“…Compared with other high-density uranium alloys and compounds, the low-enriched uranium alloys with 6-12 wt.% of Mo have attracted a great deal of attention and are recognized as the most prominent candidates in advanced research and test reactors. Mo is a strong γ-stabilizer, which provides a stable swelling behavior in U-Pu-Mo fuels, and it has high thermal conductivity, low thermal expansion, and high melting points [1][2][3][4][5].…”

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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Uranium-molybdenum alloys in reactor construction

Cited by 19 publications

References 1 publication

Corrosion report for the U-Mo fuel concept

Corrosion report for the U-Mo fuel concept

Atomic simulations of primary irradiation damage in U–Mo–Xe system

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

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