"Nuclear fuel technology" trang 1 - tải miễn phí từ tailieunhanh
Integral nuclear data validation using experimental spent nuclear fuel compositions

Integral nuclear data validation using experimental spent nuclear fuel compositions
8    147    0
Statistical model for forecasting uranium prices to estimate the nuclear fuel cycle cost

Statistical model for forecasting uranium prices to estimate the nuclear fuel cycle cost
8    126    0
Evaluation of the reutilization of used nuclear fuel in a PWR core without reprocessing

Evaluation of the reutilization of used nuclear fuel in a PWR core without reprocessing
11    92    0
Development of an evaluation method for nuclear fuel debrisefiltering performance

Development of an evaluation method for nuclear fuel debrisefiltering performance
7    87    0
Nondestructive inspection of spent nuclear fuel storage canisters using shear horizontal guided waves

Nondestructive inspection of spent nuclear fuel storage canisters using shear horizontal guided waves
9    71    0
Unsteady heat exchange at the dry spent nuclear fuel storage

Unsteady heat exchange at the dry spent nuclear fuel storage
6    101    0
Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants

Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants
8    81    0
The choice of the fuel assembly for VVER-1000 in a closed fuel cycle based on REMIX-technology

The choice of the fuel assembly for VVER-1000 in a closed fuel cycle based on REMIX-technology
7    88    0
Effect of central hole on fuel temperature distribution

Effect of central hole on fuel temperature distribution
7    72    0
Thermale - hydraulic characteristics for canflex fuel channel using burnable poison in candu reactor

Thermale - hydraulic characteristics for canflex fuel channel using burnable poison in candu reactor
8    59    0
Neutronic analysis of fuel assembly design in Small-PWR using uranium mononitride fully ceramic micro-encapsulated fuel using SCALE and Serpent codes

Neutronic analysis of fuel assembly design in Small-PWR using uranium mononitride fully ceramic micro-encapsulated fuel using SCALE and Serpent codes
12    84    0
Computational design and characterization of a subcritical reactor assembly with TRIGA fuel

Computational design and characterization of a subcritical reactor assembly with TRIGA fuel
8    84    0
Experimental simulation of activity release from leaking fuel rods

Experimental simulation of activity release from leaking fuel rods
6    78    0
Mechanical analysis of the bow deformation of a row of fuel assemblies in a PWR core

Mechanical analysis of the bow deformation of a row of fuel assemblies in a PWR core
9    62    0
Simulation of reactivity-initiated accident transients on UO2-M5® fuel rods with ALCYONE V1.4 fuel performance code

Simulation of reactivity-initiated accident transients on UO2-M5® fuel rods with ALCYONE V1.4 fuel performance code
12    67    0
Nuclide composition non-uniformity in used nuclear fuel for considerations in pyroprocessing safeguards

Nuclide composition non-uniformity in used nuclear fuel for considerations in pyroprocessing safeguards
11    81    0
An integrated multicriteria decision making approach for evaluating nuclear fuel cycle systems for long term sustainability on the basis of an equilibrium model: Technique for order of preference by similarity to ideal solution, preference ranking organization method for enrichment evaluation, and multiattribute utility theory combined with analytic hierarchy process

An integrated multicriteria decision making approach for evaluating nuclear fuel cycle systems for long term sustainability on the basis of an equilibrium model: Technique for order of preference by similarity to ideal solution, preference ranking organization method for enrichment evaluation, and multiattribute utility theory combined with analytic hierarchy process
17    114    0
Influences of heating processes on properties and microstructure of porous CeO2 beads as a surrogate for nuclear fuels fabricated by a microfluidic sol-gel process

Influences of heating processes on properties and microstructure of porous CeO2 beads as a surrogate for nuclear fuels fabricated by a microfluidic sol-gel process
6    82    0
Physical and economical aspects of Pu multiple recycling on the basis of REMIX reprocessing technology in thermal reactors

Physical and economical aspects of Pu multiple recycling on the basis of REMIX reprocessing technology in thermal reactors
7    67    0
Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor

Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor
7    74    0