"nuclear energy" trang 4 - tải miễn phí từ tailieuXANH
Iron-chrome-aluminum alloy cladding for increasing safety in nuclear power plants

Iron-chrome-aluminum alloy cladding for increasing safety in nuclear power plants
8    67    0
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    44    0
Initial economic appraisal of nuclear district heating in France

Initial economic appraisal of nuclear district heating in France
11    75    0
The impact of metrology study sample size on uncertainty in IAEA safeguards calculations

The impact of metrology study sample size on uncertainty in IAEA safeguards calculations
10    60    0
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    7    1
STRAD project for systematic treatments of radioactive liquid wastes generated in nuclear facilities

STRAD project for systematic treatments of radioactive liquid wastes generated in nuclear facilities
8    7    1
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    9    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    5    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    11    1
External heat transfer capability of a submerged SMR containment: The Flexblue case

External heat transfer capability of a submerged SMR containment: The Flexblue case
14    7    1
Development of a research reactor protocol for neutron multiplication measurements

Development of a research reactor protocol for neutron multiplication measurements
20    7    1
Preliminary analysis of an integral Small Modular Reactor operating in a submerged containment

Preliminary analysis of an integral Small Modular Reactor operating in a submerged containment
10    5    1
On the dose fields due to activated cooling water in nuclear facilities

On the dose fields due to activated cooling water in nuclear facilities
14    8    1
On nuclear-coupled thermal-hydraulic instability analysis of Super-CriticalLight-Water-cooled-reactor (SCLWR)

On nuclear-coupled thermal-hydraulic instability analysis of Super-CriticalLight-Water-cooled-reactor (SCLWR)
20    13    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    6    1
A multi-physics solver for liquid-fueled fast systems based on the discontinuous Galerkin FEM discretization

A multi-physics solver for liquid-fueled fast systems based on the discontinuous Galerkin FEM discretization
15    14    1
Radiological characterisation in view of nuclear reactor decommissioning: On-site benchmarking exercise of a biological shield

Radiological characterisation in view of nuclear reactor decommissioning: On-site benchmarking exercise of a biological shield
13    9    1
Hepa filter age evaluation and estimate of nominal lifetime in nuclear facilities

Hepa filter age evaluation and estimate of nominal lifetime in nuclear facilities
7    14    1
Assessment of dose consequences based on postulated BDBA (beyond design basic accident) A-30MWt RSG-GAS after 30-year operation

Assessment of dose consequences based on postulated BDBA (beyond design basic accident) A-30MWt RSG-GAS after 30-year operation
7    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    10    1
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