"nuclear engineering and technology" trang 14 - tải miễn phí từ tailieuXANH
On the safety and performance demonstration tests of prototype Gen-IV sodium cooled fast reactor and validation and verification of computational codes

On the safety and performance demonstration tests of prototype Gen-IV sodium cooled fast reactor and validation and verification of computational codes
13    62    0
Optimization of operation parameters of 80 kev electron gun

Optimization of operation parameters of 80 kev electron gun
8    80    0
Precise void fraction measurement in two phase flows independent of the flow regime using gamma ray attenuation

Precise void fraction measurement in two phase flows independent of the flow regime using gamma ray attenuation
8    55    1
Prediction of hydrogen concentration in containment during severe accidents using fuzzy neural network

Prediction of hydrogen concentration in containment during severe accidents using fuzzy neural network
9    54    0
Prediction of the reactor vessel water level using fuzzy neural networks in severe accident circumstances of NPPS

Prediction of the reactor vessel water level using fuzzy neural networks in severe accident circumstances of NPPS
8    65    2
Preparation and properties of the fast curing g-ray shielding materials based on polyurethane

Preparation and properties of the fast curing g-ray shielding materials based on polyurethane
8    46    0
Study of core support barrel vibration monitoring using ex core neutron noise analysis and fuzzy logic algorithm

Study of core support barrel vibration monitoring using ex core neutron noise analysis and fuzzy logic algorithm
11    57    0
Study of the effect of (U0.8Pu0.2)O2 uraniume plutonium mixed fuel fission products on a living organism

Study of the effect of (U0.8Pu0.2)O2 uraniume plutonium mixed fuel fission products on a living organism
10    35    0
Superheated water - cooled small modular underwater reactor concept

Superheated water - cooled small modular underwater reactor concept
12    64    0
The adaptation method in the monte carlo simulation for computed tomography

The adaptation method in the monte carlo simulation for computed tomography
7    83    1
The effect of hydrogen and oxygen contents on hydride reorientations of zirconium alloy cladding tubes

The effect of hydrogen and oxygen contents on hydride reorientations of zirconium alloy cladding tubes
10    51    0
The impact of power coefficient of reactivity on candu 6 reactors

The impact of power coefficient of reactivity on candu 6 reactors
8    61    0
Highly efficient adsorptive removal of uranyl ions from aqueous solutions using dicalcium phosphate nanoparticles as a superabsorbent

Highly efficient adsorptive removal of uranyl ions from aqueous solutions using dicalcium phosphate nanoparticles as a superabsorbent
8    45    0
Research on flow characteristics in supercritical water natural circulation: Influence of heating power distribution

Research on flow characteristics in supercritical water natural circulation: Influence of heating power distribution
9    72    0
Particle image velocimetry measurement of complex flow structures in the diffuser and spherical casing of a reactor coolant pump

Particle image velocimetry measurement of complex flow structures in the diffuser and spherical casing of a reactor coolant pump
11    51    0
AIMS-MUPSA software package for multi-unit PSA

AIMS-MUPSA software package for multi-unit PSA
11    58    0
Thermal transport in thorium dioxide

Thermal transport in thorium dioxide
7    49    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    45    0
Effect of a surface oxide-dispersion-strengthened layer on mechanical strength of zircaloy-4 tubes

Effect of a surface oxide-dispersion-strengthened layer on mechanical strength of zircaloy-4 tubes
5    48    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    55    0
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