"nuclear fuel for considerations in pyroprocessing safeguards" trang 4 - tải miễn phí từ tailieunhanh
Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations

Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations
11    69    0
Structural integrity assessment and stress measurement of chasnupp-1 fuel assembly skeleton: under tensile loading condition

Structural integrity assessment and stress measurement of chasnupp-1 fuel assembly skeleton: under tensile loading condition
6    94    0
Computational burnup analysis of the TRIGA Mark II research reactor fuel

Computational burnup analysis of the TRIGA Mark II research reactor fuel
21    12    1
Modelling FeCrAl cladding thermo-mechanical performance. Part I: Steady-state conditions

Modelling FeCrAl cladding thermo-mechanical performance. Part I: Steady-state conditions
13    7    1
Feasibility of minor actinide transmutation in the VVER-1000 fuel assembly

Feasibility of minor actinide transmutation in the VVER-1000 fuel assembly
11    13    1
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
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    88    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    69    0
Inert-matrix fuel for transmutation: Selected mid- and long-term effects on reprocessing, fuel fabrication and inventory sent to final disposal

Inert-matrix fuel for transmutation: Selected mid- and long-term effects on reprocessing, fuel fabrication and inventory sent to final disposal
10    14    1
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    58    0
Melt jet-breakup and fragmentation phenomena in nuclear reactors: A review of experimental works and solidification effects

Melt jet-breakup and fragmentation phenomena in nuclear reactors: A review of experimental works and solidification effects
16    10    1
Ebook The physics of nuclear reactors: Part 3

Ebook The physics of nuclear reactors: Part 3
628    6    1
Nuclear Physics The Core of Matter, The Fuel of Stars

Nuclear Physics The Core of Matter, The Fuel of Stars
222    85    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    75    0
Development status of microcell UO2 pellet for accident-tolerant fue

Development status of microcell UO2 pellet for accident-tolerant fue
6    51    0
Performance evaluation of METAMIC neutron absorber in spent fuel storage rack

Performance evaluation of METAMIC neutron absorber in spent fuel storage rack
6    59    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
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
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
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