"Nuclear fuel for considerations in pyroprocessing safeguards" trang 1 - tải miễn phí từ tailieuXANH
Spectrometry analysis of fumes of mixed nuclear fuel (U0.8Pu0.2)O2e samples heated up to 2,000с and evaluation of accidental irradiation of living organisms by plutonium as the most radiotoxic fission product of mixed nuclear fuel

Spectrometry analysis of fumes of mixed nuclear fuel (U0.8Pu0.2)O2e samples heated up to 2,000с and evaluation of accidental irradiation of living organisms by plutonium as the most radiotoxic fission product of mixed nuclear fuel
11    42    0
Integral nuclear data validation using experimental spent nuclear fuel compositions

Integral nuclear data validation using experimental spent nuclear fuel compositions
8    216    0
Statistical model for forecasting uranium prices to estimate the nuclear fuel cycle cost

Statistical model for forecasting uranium prices to estimate the nuclear fuel cycle cost
8    92    0
Evaluation of the reutilization of used nuclear fuel in a PWR core without reprocessing

Evaluation of the reutilization of used nuclear fuel in a PWR core without reprocessing
11    42    0
Shielding analysis of dual purpose casks for spent nuclear fuel under normal storage conditions

Shielding analysis of dual purpose casks for spent nuclear fuel under normal storage conditions
10    63    0
Development of an evaluation method for nuclear fuel debrisefiltering performance

Development of an evaluation method for nuclear fuel debrisefiltering performance
7    166    0
Nondestructive inspection of spent nuclear fuel storage canisters using shear horizontal guided waves

Nondestructive inspection of spent nuclear fuel storage canisters using shear horizontal guided waves
9    79    0
Unsteady heat exchange at the dry spent nuclear fuel storage

Unsteady heat exchange at the dry spent nuclear fuel storage
6    67    0
Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants

Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants
8    64    0
Nuclear fuel cycle cost estimation and sensitivity analysis of unit costs on the basis of an equilibrium model

Nuclear fuel cycle cost estimation and sensitivity analysis of unit costs on the basis of an equilibrium model
9    73    0
The choice of the fuel assembly for VVER-1000 in a closed fuel cycle based on REMIX-technology

The choice of the fuel assembly for VVER-1000 in a closed fuel cycle based on REMIX-technology
7    81    0
Cross check of the new economic and mass balance features of the fuel cycle scenario code TR_EVOL

Cross check of the new economic and mass balance features of the fuel cycle scenario code TR_EVOL
8    51    0
Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters

Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters
11    10    2
Effect of central hole on fuel temperature distribution

Effect of central hole on fuel temperature distribution
7    61    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    72    0
The use of ionising radiation to image nuclear fuel: A review

The use of ionising radiation to image nuclear fuel: A review
22    11    1
Role of the host communities in final disposal of spent nuclear fuel in Finland and Sweden

Role of the host communities in final disposal of spent nuclear fuel in Finland and Sweden
9    5    1
The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe e Part I: Uranium fuel cycle

The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe e Part I: Uranium fuel cycle
13    14    1
Thermale - hydraulic characteristics for canflex fuel channel using burnable poison in candu reactor

Thermale - hydraulic characteristics for canflex fuel channel using burnable poison in candu reactor
8    55    0
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant

Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant
5    12    1
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