World Journal of Nuclear Science and Technology

Title Publication Date Language Citations
Neutronic Analysis of Generic Heavy Water Research Reactor Core Parameters to Use Standard Hydride Fuel2011/01/018
Nuclear Power for Poland2013/01/018
Accumulation of Natural Radionuclides by Some Edible Wild Mushrooms in Ekiti State, Southwestern, Nigeria2015/01/017
Towards Safer and More Sustainable Ways for Exploiting Nuclear Power2020/01/017
Development of Diagnostics for High-Temperature High-Pressure Liquid Pb-16Li Applications2017/01/017
On the Build-Up Factor from the Multi-Group Neutron Diffusion Equation with Cylindrical Symmetry2013/01/017
Reduction of Systematic Error in Radiopharmaceutical Activity by Entropy Based Mutual Information2012/01/016
U and Th Determination in Natural Samples Using CR-39 and LR-115 Track Detectors2012/01/016
Application of Photon-Counting X-ray Computed Tomography to Aluminum-Casting Inspection2013/01/016
Study of Criticality Safety and Neutronic Performance for a 348-Fuel-Pin Ghana Research Reactor-1 LEU Core Using MCNP Code2014/01/016
Diagnostic Reference Level in Frontal Chest X-Ray in Western Côte d’Ivoire2019/01/016
Quality Assessment Statistic Evaluation of X-Ray Fluorescence via NIST and IAEA Standard Reference Materials2017/01/016
Experimental and Simulated Effective Dose for Some Building Materials in France2013/01/016
Radon Awareness among Saudi People in Riyadh, Saudi Arabia2012/01/016
Computing Efficiency Improvement in Monte Carlo Simulation of a 12 MV Photon Beam Medical LINAC2013/01/016
Recovery of Rare Earth Elements Present in Mining Tails, by Leaching with Nitric and Hydrochloric Solutions2021/01/016
Engineering of Fuel Plates on Uranium-Molybdenum Monolithic: Critical Issues2015/01/015
The Diffusion of Tc-99 in Beishan Granite-Temperature Effect2013/01/015
A Study on the Cause Analysis for the Wall Thinning and Leakage in Small Bore Piping Downstream of Orifice2014/01/015
Feasibility to Convert the NuScale SMR from UO<sub>2</sub> to a Mixed (U, Th)O<sub>2</sub> Core: A Parametric Study of Fuel Element—Seed-Blanket Concept2023/01/015
Localization of Plastic Deformation in Copper Canisters for Spent Nuclear Fuel2012/01/015
Gamma Radiation Measurements in Tunisian Marbles2012/01/015
Control Rod Calibration and Worth Calculation for Optimized Power Reactor 1000 (OPR-1000) Using Core Simulator OPR10002017/01/015
Method to Measure Indoor Radon Concentration in an Open Volume with Geiger-Mueller Counters: Analysis from First Principles2016/01/015
Effect of Potential Energy Stored in Reactor Facility Coolant on NPP Safety and Economic Parameters2013/01/015
Validation of RELAP5/MOD3.2 Code for Flashing-Induced Instabilities in a Single Channel2015/01/015
SVBR-100 Nuclear Technology as a Possible Option for Developing Countries2015/01/015
Neutron Induced Fission Track Estimation of Uranium Concentration and Its Associated Health Hazards in Drinking Water of the Faisalabad Industrial City2013/01/014
Characteristics of Filtered Neutron Beam Energy Spectra at Dalat Reactor2014/01/014
Development of ToSPACE for Pipe Wall Thinning Management in Nuclear Power Plants2019/01/014