Results 181 to 190 of about 3,656,066 (246)
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The anodic oxidation of uranium

Acta Metallurgica, 1954
Abstract Over a range of 2–100 volts the anodic oxidation of uranium in ammoniacal ethylene glycol produces oxide films which are predominantly uranium dioxide in composition. The oxide formed in this manner shows considerable stability to atmospheric corrosion.
O Flint, J.J Polling, A Charlesby
openaire   +1 more source

Irradiation testing of enhanced uranium oxide fuels

Annals of Nuclear Energy, 2019
Enhanced uranium oxide fuel types are being tested in the Halden Research Reactor in Norway with the aim is to assess the effect that these enhancements have on fuel performance.
K. I. Björk   +13 more
semanticscholar   +1 more source

Assembly of three-dimensional ultralight poly(amidoxime)/graphene oxide nanoribbons aerogel for efficient removal of uranium(VI) from water samples.

Science of the Total Environment, 2020
Assembling graphene oxide nanoribbons (GONRs) into three-dimensional (3D) materials with controllable and desired structure is an effective way to expand their structural features and enable their practical applications.
Yun Wang   +12 more
semanticscholar   +1 more source

Highly efficient removal of uranium from highly acidic media achieved using a phosphine oxide and amino functionalized superparamagnetic composite polymer adsorbent

Journal of Materials Chemistry A, 2020
The magnetic adsorbent Fe3O4/P(DMAA–DMP) prepared by distillation-precipitation polymerization not only showed an outstanding adsorption efficiency for uranium in highly acidic solution, but had an excellent acid resistance.
Shiao Zhang   +6 more
semanticscholar   +1 more source

Application of HRGS for forensic characterization of uranium oxides, pure uranium metals and uranium alloys

Applied Radiation and Isotopes, 2021
A nondestructive iterative method for uranium-bearing material characterization with HRGS developed earlier in Burdeinyi et al. (2020) is applied to determine matrix densities, uranium mass fraction and uranium isotope masses of uranium ore, UO2 and U3O8 powders, fuel elements in the form of UO2 microspheres, uranium metal and uranium alloys.
D. Burdeinyi   +6 more
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A chitosan-graphene oxide/ZIF foam with anti-biofouling ability for uranium recovery from seawater

, 2020
Biofouling is the most affecting factor in the recovery of uranium due to the presence of large number of marine microorganisms in the seawater. Herein, a chitosan – graphene oxide/ZIF (GCZ8A) foam adsorbent with antifouling properties was prepared via ...
Xuejie Guo   +10 more
semanticscholar   +1 more source

Uranium oxide synthetic pathway discernment through thermal decomposition and morphological analysis

Radiochimica Acta, 2018
Many commercial processes exist for converting uranium from ore to the desired uranium compound for use in nuclear power or nuclear weapons. Accurately determining the processing history of the uranium ore concentrates (UOCs) and their calcination ...
I. Schwerdt   +5 more
semanticscholar   +1 more source

Oxidation of uranium monocarbide

Journal of the Less Common Metals, 1962
Abstract Compacts of uranium monocarbide with a density of 11.7–12.7 g/cm 3 have been oxidized in I atm of CO 2 , O 2 , N 2 and CO at temperatures in the range 350–1000°C and all the reactions found to obey a linear rate law. The linear rate constants increased as the temperature increased and the density decreased, and for dense compacts were ...
K.A. Peakall, J.E. Antill
openaire   +1 more source

Synthesis and characterization of multi-carboxyl functionalized nanocellulose/graphene oxide-zinc oxide composite for the adsorption of uranium (VI) from aqueous solutions: Kinetic and equilibrium profiles

Materials Today: Proceedings, 2020
The present study is the preparation of the novel adsorbent, multi-carboxyl-functionalized Nanocellulose/Graphene Oxide-Zinc Oxide composite for the removal of Uranium. Fourier transforms infrared spectroscopy (FTIR), X-ray diffraction (XRD) and Scanning
A. Radhakrishnan, J. Nahi, B. Beena
semanticscholar   +1 more source

Oxidation of uranium mononitride

Journal of Nuclear Materials, 1975
Abstract The oxidation of powdered uranium mononitride begins at 200°C by a slow absorption of oxygen. Weakly crystallized products, U 2 N 3 and UO 2 , are formed. An intensive incorporation of oxygen occurs at 250° C accompanied by a loss of nitrogen. Simultaneously, the amount of U 2 N 3 diminishes and the α-UO 3 phase appears.
M Paljević, Z Despotović
openaire   +1 more source

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