The distribution of and swelling produced by fission gas bubbles in α and β uranium irradiated under low stress

Hudson, B.

doi:10.1016/0022-3115(67)90022-0

Cited by 21 publications

(3 citation statements)

References 20 publications

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“…Finally, the (001) surface energy is calculated and shown to match with experiment, but it is substantially smaller than other MD results and the two independent GGA calculations. Reference: a [20]; b [9]; c [18]; d [29]; e [34]; f [35].…”

Section: Comparison Of the Comb And Eam Potentialmentioning

confidence: 99%

Lattice expansion by intrinsic defects in uranium by molecular dynamics simulation

Chernatynskiy

Kennedy

et al. 2016

Journal of Nuclear Materials

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Section: Comparison Of the Comb And Eam Potentialmentioning

confidence: 99%

Lattice expansion by intrinsic defects in uranium by molecular dynamics simulation

Chernatynskiy

Kennedy

et al. 2016

Journal of Nuclear Materials

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“…It should be smaller than the actual value due to the mosaic structure of the sample. Additionally, there are three other activation energy values reported in the literature (1.99 eV [22,23], 2.15 eV [24,25] and 2.21 eV [26,27]), which do not specify the direction. All of these values are within the range 1.91-2.91 eV.…”

Section: Introductionmentioning

confidence: 99%

First-principles study of diffusion of interstitial and vacancy in α U–Zr

Huang

Wirth

2011

J. Phys.: Condens. Matter

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Metallic uranium-zirconium alloys are of interest for a variety of fast reactor designs, and there is substantial experience with the behavior of metallic fuels. Yet, there remain a number of questions regarding the mechanisms controlling fission-gas-driven swelling in these alloys. Here we present results of ab initio calculations of the diffusion behavior of interstitial and vacancy point defects in α U-Zr alloys. The formation energy and migration barrier of vacancy and interstitial defects, and the influence of Zr on these values, is obtained and compared with experimental results. Our results confirm that self-diffusion in pure α U is via a simple vacancy mechanism, and shows anisotropic character. The calculated values of activation energy are consistent with the experimental results in the literature. For interstitial diffusion, the kick-out mechanism was found to have the smallest energy barrier. The calculations of point defects, and later Xe, in U-Zr alloys will provide a foundation for computational modeling of fission gas bubble nucleation and growth.

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“…3). It should be noted that according to existing ideas [6,7], a structure with substantially smaller pores is formed in uranium and its alloys under irradiation -the average pore diameter is 0.005-0.05 µm and the number of pores reaches 7·10 15 cm -3 . Apparently, the methods used to perform the investigations made it possible to observe only the largest pores.…”

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confidence: 99%

Radiation resistance of high-density uranium—molybdenum dispersion fuel for nuclear research reactors

et al. 2006

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The results of radiation tests are discussed and the character of the failure of fuel compositions and the operability of fuel elements is analyzed as a function of the type of fuel and the irradiation conditions. The intense interaction of the fuel with the matrix material is considered as the main factor limiting the operability of fuel elements in power-dense high-flux nuclear reasearch reactors. It is concluded that low-enrichment high-density uranium-molybdenym fuel can provide reliable operation of dispersion fuel elements in low-and medium-power research reactors. Such fuel can be used in power-dense high-flux research reactors if the fuel load is decreased below the maximum admissible amount, the compatibility of the uranium-molybdenum alloy with an aluminum matrix is radically improved, or fuel elements with a different construction, for example, monolithic, are used.A large number of radiation tests of new types of dispersion fuel have been conducted as part of the international program on decreasing the enrichment of fuel for research reactors (RERTR) and national programs [1][2][3][4][5]. Plate-shaped miniscale fuel elements with dispersion fuel based on various high-density alloys and uranium compounds have been tested at the first stage. Fuel based on uranium silicide U 3 Si 2 and uranium alloys with 7-10% molybdenum or zirconium and niobium with total content at least 10% exhibited the best radiation resistance. Consequently, mini-and full-scale fuel elements with fuel based on these alloys, primarily, uranium alloys with molybdenum (here and below, the mass fraction of the alloying element is given in %) were tested in further tests.The influence of the characteristics of the dispersion fuel and the conditions of irradiation on the radiation resistance of fuel elements were investigated in the experiments. The results obtained make it possible to draw conclusions about the regularities in the behavior of, the failure of fuel compositions of, and the operability of fuel elements as a function of the type of fuel and conditions of irradiation.Results of the First Stage of the Investigations. At the first stage of the investigations, the RERTR-1 and -2 computer programs were used to study the radiation resistance of plate-shaped miniscale fuel elements with fuel based on intermetallic compounds of uranium with iron, manganese, silicon, and aluminum and alloys of uranium with molybdenum, zirconium, and niobium. The uranium content in the composition was 4 g/cm 3 , the heat flux and temperature of the fuel-element cladding were 55 W/cm 2 and 65°C, respectively, and the burnup 40 and 70% 235 U.Some of the fuel elements successfully withstood the tests -they remain sealed, and the increase in the thickness of the plates was negligible. The microstructure of the fuel composition of such fuel elements after irradiation in the reactor was essentially identical to the initial microstructure (Fig. 1). The fuel particles retained their shape and size. The interaction of

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The distribution of and swelling produced by fission gas bubbles in α and β uranium irradiated under low stress

Cited by 21 publications

References 20 publications

Lattice expansion by intrinsic defects in uranium by molecular dynamics simulation

Lattice expansion by intrinsic defects in uranium by molecular dynamics simulation

First-principles study of diffusion of interstitial and vacancy in α U–Zr

Radiation resistance of high-density uranium—molybdenum dispersion fuel for nuclear research reactors

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