| The heavy metal oxide glasses within the WO3-MoO3-TeO2 system to investigate the shielding properties of radiation applications |
46 |
| Comparison study of photon attenuation characteristics of Poly vinyl alcohol (PVA) doped with Pb(NO3)(2) by MCNP5 code, XCOM and experimental results |
22 |
| Fusible alloys: A potential candidate for gamma rays shield design |
20 |
| Estimation of gamma radiation shielding qualification of newly developed glasses by using WinXCOM and MCNPX code |
19 |
| Adsorption of uranium (VI) by amidoxime modified multiwalled carbon nanotubes |
17 |
| A review of ground-based robotic systems for the characterization of nuclear environments |
15 |
| Review on scope of metallic alloys in gamma rays shield designing |
14 |
| Research on intelligent fault diagnosis method for nuclear power plant based on correlation analysis and deep belief network |
14 |
| Numerical research on thermal mixing characteristics in a 45-degree T-junction for two-phase stratified flow during the emergency core cooling safety injection |
13 |
| Study on gamma shielding polymer composites reinforced with different sizes and proportions of tungsten particles using MCNP code |
10 |
| The maturing of nuclear fuel: Past to Accident Tolerant Fuel |
10 |
| Optimal design of supercritical CO2 power cycle for next generation nuclear power conversion systems |
10 |
| Adsorptive removal of radioactive isotopes of cobalt and zinc from water and radioactive wastewater using TiO2/Ag2O nanoadsorbents |
10 |
| The thermodynamic and cost-benefit-analysis of miniaturized lead-cooled fast reactor with supercritical CO2 power cycle in the commercial market |
10 |
| Enhancement of flame retardancy and radiation shielding properties of ethylene vinyl acetate based radiation shielding composites by EB irradiation |
10 |
| Optimization of Th-U fuel breeding based on a single-fluid double-zone thorium molten salt reactor |
9 |
| Robotic delivery of laser-induced breakdown spectroscopy for sensitive chlorine measurement in dry cask storage systems |
9 |
| Investigation of usability of limonite aggregate in heavy-weight concrete production |
9 |
| Knowledge base operator support system for nuclear power plant fault diagnosis |
8 |
| Review: Condensation regime maps of steam submerged jet condensation |
8 |
| Characterization of biological waste stabilized by cement during immersion in aqueous media to develop disposal strategies for phytomediated radioactive waste |
8 |
| GEN-IV LFR development: Status & perspectives |
8 |
| Removal of cobalt ions from simulated radioactive wastewater by vacuum membrane distillation |
8 |
| Developments of analyses on grid-to-rod fretting problems in pressurized water reactors |
8 |
| Three-dimensional study on the hydraulic characteristics under the steam generator (SG) tube plugging operations for AP1000 |
8 |
| Removal of radionuclides from a HC1 steel decontamination stream using chelating ion exchange resins - Initial studies |
7 |
| Experimental and CFD estimation of single-phase heat transfer in helically coiled tubes |
7 |
| Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium |
7 |
| Gamma exposure buildup factors and neutron total cross section of ceramic hosts for high level radioactive wastes |
7 |
| A review of separation processes proposed for advanced fuel cycles based on technology readiness level assessments |
7 |
| Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors |
7 |
| Development and verification of the high-fidelity neutronics and thermal hydraulic coupling code system NECP-X/SUBSC |
7 |
| Improved leakage splitting method for the 2D/1D transport calculation |
7 |
| Probabilistic roadmap method for path-planning in radioactive environment of nuclear facilities |
6 |
| The material characterization and gamma attenuation properties of Portland cement-Fe3O4 composites for potential dry cask applications |
6 |
| A nonlinear adaptive sliding mode control strategy for modular high-temperature gas-cooled reactors |
6 |
| A Haar wavelet method for angularly discretising the Boltzmann transport equation |
6 |
| Advanced BWR criticality safety part I: Model development, model benchmarking, and depletion with uncertainty analysis |
6 |
| Removal of nuclides and boric acid from simulated radioactive wastewater by forward osmosis |
6 |
| A code development for leak before break (LBB) leakage from supercritical to subcritical conditions |
6 |
| Robust tuned PID controller with PSO based on two-point kinetic model and adaptive disturbance rejection for a PWR-type reactor |
6 |
| Investing in a permanent and sustainable nuclear waste disposal solution |
6 |
| Safety analysis of Super-Critical Water Reactors-A review |
6 |
| Measurement on effective thermal diffusivity and conductivity of pebble bed under vacuum condition in High Temperature Gas-cooled Reactor |
6 |
| Simultaneous adsorption of uranium(VI) and phosphate on red clay |
6 |
| EVAL: A methodological approach to identify NPP total capital investment cost drivers and sensitivities |
6 |
| Preparation, shielding properties and mechanism of a novel neutron shielding material made from natural Szaibelyite resource |
5 |
| Flexible X/Gamma ray shielding composite material of EPDM rubber with bismuth trioxide: Mechanical, thermal investigations and attenuation tests |
5 |
| Assessment of neutron shielding performance of nano-TiO2-incorporated cement paste by Monte Carlo simulation |
5 |
| High-order lattice Boltzmann method for multi-group neutron diffusion solution |
5 |
