"fuel transport system" trang 7 - tải miễn phí từ tailieunhanh
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
Modeling of central void formation in LWR fuel pellets due to high-temperature restructuring

Modeling of central void formation in LWR fuel pellets due to high-temperature restructuring
8    85    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
Thermal shock fracture of silicon carbide and its application to lwr fuel cladding performance during reflood

Thermal shock fracture of silicon carbide and its application to lwr fuel cladding performance during reflood
10    80    0
U.s. fuel cycle technologies R&D program for next generation nuclear materials management

U.s. fuel cycle technologies R&D program for next generation nuclear materials management
8    102    0
Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage

Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage
8    121    0
Natural convection heat transfer characteristics in a canister with horizontal installation of dual purpose cask for spent nuclear fuel

Natural convection heat transfer characteristics in a canister with horizontal installation of dual purpose cask for spent nuclear fuel
10    60    0
Irradiation device for irradiation testing of coated particle fuel at HANARO

Irradiation device for irradiation testing of coated particle fuel at HANARO
10    51    0
Modeling of pore coarsening in the rim region of high burn up UO2 fuel

Modeling of pore coarsening in the rim region of high burn up UO2 fuel
7    52    0
Nuclear data uncertainty and sensitivity analysis with xsusa for fuel assembly depletion calculations

Nuclear data uncertainty and sensitivity analysis with xsusa for fuel assembly depletion calculations
10    70    0
Nuclear data uncertainty propagation for a typical pwr fuel assembly with burnup

Nuclear data uncertainty propagation for a typical pwr fuel assembly with burnup
10    73    0
Steady - and transient state analyses of fully ceramic microencapsulated fuel with randomly dispersed tristructural isotropic particles via two temperature homogenized modeldii: Applications by coupling with coredax

Steady - and transient state analyses of fully ceramic microencapsulated fuel with randomly dispersed tristructural isotropic particles via two temperature homogenized modeldii: Applications by coupling with coredax
13    78    0
Summary of materials science doctoral thesis: Synthesis and characterization of carbon supported Pt and Pt alloy nanoparticles as electrocatalysts material for proton exchange membrane fuel cell

Summary of materials science doctoral thesis: Synthesis and characterization of carbon supported Pt and Pt alloy nanoparticles as electrocatalysts material for proton exchange membrane fuel cell
22    94    0
Microstructure and residual properties of green concrete composites incorporating waste carpet fibers and palm oil fuel ash at elevated temperatures

Microstructure and residual properties of green concrete composites incorporating waste carpet fibers and palm oil fuel ash at elevated temperatures
14    95    2
Predicting behavior of AP-1000 nuclear reactor fuel rod under steady state operating condition by using FRAPCON-4.0 software

Predicting behavior of AP-1000 nuclear reactor fuel rod under steady state operating condition by using FRAPCON-4.0 software
8    53    0
Calculation of neutronic characteristics in different reflector materials with a 15-MWt reactor core using VVR-KN fuel type

Calculation of neutronic characteristics in different reflector materials with a 15-MWt reactor core using VVR-KN fuel type
7    53    2
Chemical kinetic simulation of kerosene combustion in an individual flame tube

Chemical kinetic simulation of kerosene combustion in an individual flame tube
10    68    0
Effect of strontium on Nd doped Ba1 xSrxCe0.65Zr0.25Nd0.1O3 d proton conductor as an electrolyte for solid oxide fuel cells

Effect of strontium on Nd doped Ba1 xSrxCe0.65Zr0.25Nd0.1O3 d proton conductor as an electrolyte for solid oxide fuel cells
13    59    0
Empirical equations and economical study for blending biofuel with petroleum jet fuel

Empirical equations and economical study for blending biofuel with petroleum jet fuel
8    100    0
Preparation and physical properties of (PVA)0.7(NaBr)0.3(H3PO4)xM solid acid membrane for phosphoric acid – Fuel cells

Preparation and physical properties of (PVA)0.7(NaBr)0.3(H3PO4)xM solid acid membrane for phosphoric acid – Fuel cells
7    101    0