nuclear fuel technology trang 2 tải miễn phí từ TAILIEUCHUNG

"nuclear fuel technology" trang 2 - tải miễn phí từ Tailieuchung

Criticality benchmark of McCARD Monte Carlo code for light-water-reactor fuel in transportation and storage packages

Criticality benchmark of McCARD Monte Carlo code for light-water-reactor fuel in transportation and storage packages

13 57 0

On the effect of temperature on the threshold stress intensity factor of delayed hydride cracking in light water reactor fuel cladding

On the effect of temperature on the threshold stress intensity factor of delayed hydride cracking in light water reactor fuel cladding

5 72 0

Investigation of molten fuel coolant interaction phenomena using real time X-ray imaging of simulated woods metal-water system

Investigation of molten fuel coolant interaction phenomena using real time X-ray imaging of simulated woods metal-water system

9 52 0

Monte Carlo analysis of LWR spent fuel transmutation in a fusionfission hybrid reactor system

Monte Carlo analysis of LWR spent fuel transmutation in a fusionfission hybrid reactor system

10 80 0

Post irradiation analyses of U-MO dispersion fuel rods of komo tests at HANARO

Post irradiation analyses of U-MO dispersion fuel rods of komo tests at HANARO

12 31 0

Thermal-hydraulics analysis for VVR-KN fuel lead test using PLTEMP code

Thermal-hydraulics analysis for VVR-KN fuel lead test using PLTEMP code

7 60 1

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 52 0

A study on the mechanically equivalent surrogate plate of UeMo dispersion fuel using tungsten

A study on the mechanically equivalent surrogate plate of UeMo dispersion fuel using tungsten

6 78 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 59 0

Experimental validation of a nuclear forensics methodology for source reactor-type discrimination of chemically separated plutonium

Experimental validation of a nuclear forensics methodology for source reactor-type discrimination of chemically separated plutonium

10 49 0

Numerical investigation on vortex behavior in wire-wrapped fuel assembly for a sodium fast reactor

Numerical investigation on vortex behavior in wire-wrapped fuel assembly for a sodium fast reactor

11 56 0

Development status of microcell UO2 pellet for accident-tolerant fue

Development status of microcell UO2 pellet for accident-tolerant fue

6 43 0

Performance evaluation of METAMIC neutron absorber in spent fuel storage rack

Performance evaluation of METAMIC neutron absorber in spent fuel storage rack

6 43 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 64 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

8 104 0

Irradiation device for irradiation testing of coated particle fuel at HANARO

Irradiation device for irradiation testing of coated particle fuel at HANARO

10 42 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 66 0

Drop formation at submerged nozzles: Comparison of aqueous dispersed and organic dispersed cases for TBP-dodecane and nitric acid system

Drop formation at submerged nozzles: Comparison of aqueous dispersed and organic dispersed cases for TBP-dodecane and nitric acid system

8 69 0

Transfer characteristics of a lithium chlorideepotassium chloride molten salt

Transfer characteristics of a lithium chlorideepotassium chloride molten salt

6 81 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 44 1

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