"nuclear fuel for considerations in pyroprocessing safeguards" trang 3 - tải miễn phí từ tailieunhanh
Storage of thermal reactor fuels – Implications for the back end of the fuel cycle in the UK

Storage of thermal reactor fuels – Implications for the back end of the fuel cycle in the UK
9    83    0
Sensitivity and uncertainty analysis on reactivity for HEU and LEU fuel assemblies of dalat nuclear research reactor using monte carlo code and ENDF/B-VII.0 and ENDF/B-VII.1 nuclear libraries

Sensitivity and uncertainty analysis on reactivity for HEU and LEU fuel assemblies of dalat nuclear research reactor using monte carlo code and ENDF/B-VII.0 and ENDF/B-VII.1 nuclear libraries
14    28    1
Study of experimental core configuration of the modified STACY for measurement of criticality characteristics of fuel debris

Study of experimental core configuration of the modified STACY for measurement of criticality characteristics of fuel debris
8    12    1
The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe e Part II: Thorium fuel cycle

The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe e Part II: Thorium fuel cycle
12    9    1
Development of an equilibrium loading pattern and whole-core fuel performance assessment in the Advanced Boiling Water Reactor (ABWR) with UO2 and U3Si2 fuels

Development of an equilibrium loading pattern and whole-core fuel performance assessment in the Advanced Boiling Water Reactor (ABWR) with UO2 and U3Si2 fuels
13    14    1
Quantifying water in spent fuel assemblies with neutrons: A simulation-based approach

Quantifying water in spent fuel assemblies with neutrons: A simulation-based approach
25    13    1
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations

Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations
7    5    1
Comparative analysis of the differential evolution and genetic algorithm applied to the nuclear reactor fuel reloading optimization

Comparative analysis of the differential evolution and genetic algorithm applied to the nuclear reactor fuel reloading optimization
9    13    1
Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor

Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor
7    74    0
Development of Cr cold sprayecoated fuel cladding with enhanced accident tolerance

Development of Cr cold sprayecoated fuel cladding with enhanced accident tolerance
8    62    0
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    70    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    82    0
Three dimensional flow phenomena in a wire wrapped 37-pin fuel bundle for sfr

Three dimensional flow phenomena in a wire wrapped 37-pin fuel bundle for sfr
11    68    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    65    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    100    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    36    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    77    2
Partitioning and transmutation strategy R&D for nuclear spent fuel: the SACSESS and GENIORS projects

Partitioning and transmutation strategy R&D for nuclear spent fuel: the SACSESS and GENIORS projects
8    95    0
Structural integrity assessment and stress measurement of CHASNUPP-1 fuel assembly Part A: under tensile loading condition

Structural integrity assessment and stress measurement of CHASNUPP-1 fuel assembly Part A: under tensile loading condition
6    83    0
Three-component U-Pu-Th fuel for plutonium irradiation in heavy water reactors

Three-component U-Pu-Th fuel for plutonium irradiation in heavy water reactors
12    91    0