International Journal of Nuclear Energy Science and Engineering

Title Publication Date Language Citations
Kinetics of Leaching Process Using Sulfuric Acid for Sella Uranium Ore Material, South Eastern Desert, Egypt2016/01/01English24
Thermal Performance of UO2-BeO Fuel during a Loss of Coolant Accident2015/01/01English7
Kinetics Leaching Process of Uranium Ions from El-Erediya Rock by Sulfuric Acid Solution2016/01/01English6
Study on Influence of Rewetting on Conduction Heat Transfer for AHWR Fuel Bundle Re-flooding Phenomena2013/01/01English6
Experimental Investigation on the Effects of a Spacer Grid on Single- and Two-Phase Flows2014/01/01English5
Quenching Behaviour of Top Flooded Molten Pool2014/01/01English4
Prospects of Nuclear Energy for Sustainable Energy Development in Bangladesh2015/01/01English3
Radioactivity and Chemical Compositions of Some Selected Commercial Bottled Waters in Belarus2014/01/01English2
Uranium (VI) Complexation with Siderophores-pyoverdine Produced by Pseudomonas Fluorescens SHA 2812013/01/01English2
Simple Configuration Setup for Compton Suppression Spectroscopy2013/01/01English2
Protection of a Nuclear Reactor Monitoring System against Gross Measurement Errors2015/01/01English2
Characterization and Application of 2-Amino-3-(4-bromophenylazo)-8, 9-Dihydro-7H-Pyrazolo [1,5-a]Quinazolin-6-One in Solvent Extraction of Uranium (VI)2017/01/01English2
Several Research Methods Introduction on NPP Operators Reliability2016/01/01English1
Prediction of the Equivalent Radon Exhalation Rate of Uranium Ore-rock in the Course of Mine Ventilation Based on GA-SVM2013/01/01English1
Natural Radioactivity Assessment of El-Sebeaya Low Grade Phosphate Rock and Hydrochloric Acid Leaching Residue2016/01/01English1
Uranium Extraction from El- Hammamat Sediment, Eastern Desert, Egypt Using Solvent-in-Pulp Technique2016/01/01English1
Gadolinium Vizualization in Vivo for Dosimetry in Neutron Capture Therapy2014/01/01English1
Fission Product Decay Heat Calculations for Thermal Neutron Fission of 235U2014/01/01English1
Definition and Expression of Thermal Neutron Effective Proliferation Coefficient in the Uniformity Dispersion Nuclear Reactor with Uniformity Dispersion Source Neutrons2014/01/01English
Design and Development of Virtual Panels for Handling Control Room in PFBR Simulator2014/01/01English
Concept for the WWR-M Reactor Renovation2014/01/01English
Experimental and Analytical Study of a Simulated Collapsed PHWR Reactor Channel Under Accident Condition2013/01/01English
Measuring Scattered X-Ray Rate at Medical Diagonistic Room Utilizing Geiger-Muller Counter2017/01/01English
The Introduction to the Solution Method of Thermal Neutron Effective Proliferation Coefficient of Any Point in the Non-uniformity Dispersion Reactor with Non-uniformity Dispersion Source Neutrons2014/01/01English
Fuel Thermo-Mechanical Performance during Transient Events in Laguna Verde Nuclear Power Plant with FETMA Code2014/01/01English
Analysis of the 2-D C5G7 MOX Benchmark with VISWAM Code2015/01/01English
The Foundation of Critical and Non-critical Neutrons Equilibrium Equations in Uniformity Dispersion Reactor with Delayed Release Neutrons and the Calculation of Relevant Parameters2014/01/01English
Co-Adsorption and Separate Elution of Uranium and Thorium from Acid Solution of Egyptian Monazite by Solvent Impregnated Foam2016/01/01English