"nuclear fuel for considerations in pyroprocessing safeguards" trang 5 - tải miễn phí từ tailieunhanh
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
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
Dose and temperature distribution in spent fuel containing material

Dose and temperature distribution in spent fuel containing material
6    98    0
Characterization of neutron spectrum parameters at irradiation channels for neutron activation analysis after full conversion of the Dalat nuclear research reactor to low enriched uranium fuel

Characterization of neutron spectrum parameters at irradiation channels for neutron activation analysis after full conversion of the Dalat nuclear research reactor to low enriched uranium fuel
6    41    3
CANDU-6 fuel optimization for advanced cycles

CANDU-6 fuel optimization for advanced cycles
14    17    1
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    84    0
Transfer characteristics of a lithium chlorideepotassium chloride molten salt

Transfer characteristics of a lithium chlorideepotassium chloride molten salt
6    99    0
Validation of UNF-ST&DARDS As-loaded safety analysis methods for BWR decay heat calculations

Validation of UNF-ST&DARDS As-loaded safety analysis methods for BWR decay heat calculations
25    14    1
The effect of organic retarders on grout thickening and setting during deep borehole disposal of high-level radioactive waste

The effect of organic retarders on grout thickening and setting during deep borehole disposal of high-level radioactive waste
8    7    1
The MARINE experiment: Irradiation of sphere-pac fuel and pellets of UO2x for americium breading blanket concept

The MARINE experiment: Irradiation of sphere-pac fuel and pellets of UO2x for americium breading blanket concept
11    9    1
Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit

Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit
15    10    1
A deterministic model for criticality and rod worth analysis of the DNRR research reactor with HEU fuel

A deterministic model for criticality and rod worth analysis of the DNRR research reactor with HEU fuel
7    17    1
Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes

Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes
9    70    0
End Points

End Points
29    48    0
STRATEGY FOR THE MANAGEMENT AND DISPOSAL OF USED NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE

STRATEGY FOR THE MANAGEMENT AND DISPOSAL OF USED NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE

18    89    0
Numerical analysis on the rapid fire suppression using a water mist nozzle in a fire compartment with a door opening

Numerical analysis on the rapid fire suppression using a water mist nozzle in a fire compartment with a door opening
14    85    0
Impact of thermal and chemical treatment on the mechanical properties of E110 and E110G cladding tubes

Impact of thermal and chemical treatment on the mechanical properties of E110 and E110G cladding tubes
8    72    0
Stratified steam explosion energetics

Stratified steam explosion energetics
9    68    0
Electromagnetism mechanism for enhancing the refueling cycle length of a wwer 1000

Electromagnetism mechanism for enhancing the refueling cycle length of a wwer 1000
11    84    0
Mechanical analysis of surface-coated zircaloy cladding

Mechanical analysis of surface-coated zircaloy cladding
13    52    0