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 Uranium Zirconium Acid Zirconium dioxide Zirconium alloy Y alloy X-ray crystallography Uranyl nitrate Triangle Transuranium element Nuclear fuel PH Thorium Ion Sorption Scanning electron microscope Spectroscopy Lead Gene Protein Antioxidant Tetragonal crystal system Aluminium oxide Supercritical water oxidation Supercritical fluid Yttrium Transmission electron microscopy Titanium Infrared spectroscopy Adsorption Uranium dioxide Sodium aluminium phosphate Sodium Phosphate Graph theory Algorithm Trapezoid Simplex Headword Nuclear safety and security Nuclear reprocessing Nuclear proliferation
RELATED SUBJECTS:
The publications listed also have these subjects
Uranium  5 times
Zirconium  2 times
Acid  2 times
Zirconium dioxide  1 time
X-ray crystallography  1 time
Triangle  1 time
Transmission electron microscopy  1 time
Test cricket  1 time
Superposition principle  1 time
Supercritical fluid  1 time
Speciation  1 time
Sodium  1 time
Shear stress  1 time
Shear modulus  1 time
Reynolds number  1 time
Redox  1 time
Plutonium  1 time
Physics  1 time
Phonon  1 time
Partial pressure  1 time
PH  1 time
Nuclear fission  1 time
Nitride  1 time
Nitrate  1 time
Monoclinic crystal system  1 time
Ion  1 time
Graphite  1 time
Fluid dynamics  1 time
Entropy  1 time
Electrolyte  1 time
Carbon dioxide  1 time
Caesium-137  1 time
Ansys  1 time

Publications tagged with this subject: 11

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1. Fast Zirconium Oxidation Using Supercritical Water

2. Integral Material Studies of Nuclear Fuel at Institute of Reactor Materials

3. Analysis of features of hydrodynamics and heat transfer in the fuel assembly of prospective sodium reactor with a high rate of reproduction in the uranium-plutonium fuel cycle

4. Steam Oxidation Evaluation of Fe–Cr Alloys for Accident Tolerant Nuclear Fuel Cladding

5. Observed Changes in As-Fabricated U-10Mo Monolithic Fuel Microstructures After Irradiation in the Advanced Test Reactor

6. An accurate and efficient analytical method for 1D hexagonal quasicrystal coating based on Green’s function

7. Further Studies on the Recycle of Pyroprocessed Uranium

8. Modeling Speciation and Solubility in Aqueous Systems Containing U(IV, VI), Np(IV, V, VI), Pu(III, IV, V, VI), Am(III), and Cm(III)

9. Thermal–hydraulic performance analysis of a subchannel with square and triangle fuel rod arrangements using the entropy generation approach

10. Technology and Facility for Incinerating Irradiated Reactor Graphite

11. Mathematical Simulation of the Crystallization Process in a Continuous Linear Crystallizer


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