The thermal hydraulic analysis trang 1 tải miễn phí từ TAILIEUCHUNG

"The thermal hydraulic analysis" trang 1 - tải miễn phí từ Tailieuchung

Multivariate analysis of critical parameters influencing the reliability of thermal-hydraulic passive safety system

Multivariate analysis of critical parameters influencing the reliability of thermal-hydraulic passive safety system

9 91 0

Sensitivity analysis of thermal-hydraulic parameters to study the corrosion intensity in nuclear power plant steam generators

Sensitivity analysis of thermal-hydraulic parameters to study the corrosion intensity in nuclear power plant steam generators

8 79 0

Thermal hydraulic analysis of core flow bypass in a typical research reactor

Thermal hydraulic analysis of core flow bypass in a typical research reactor

6 60 0

Thermal hydraulic simulations of the Angra 2 PWR

Thermal hydraulic simulations of the Angra 2 PWR

8 61 0

Neutronics characterization of an erbia fully poisoned PWR assembly by means of the APOLLO2 code

Neutronics characterization of an erbia fully poisoned PWR assembly by means of the APOLLO2 code

12 55 0

Safety analysis methodology for aged candu nuclear reactors

Safety analysis methodology for aged candu nuclear reactors

8 49 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 60 1

A sensitivity study of physical models using in RELAP5 code based on FEBA experimental data

A sensitivity study of physical models using in RELAP5 code based on FEBA experimental data

17 45 3

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 2 1

An analysis of air-water flow phenomena due to a pipe break under sub-atmospheric pressures using TRACE

An analysis of air-water flow phenomena due to a pipe break under sub-atmospheric pressures using TRACE

11 1 1

Comparison of CATHARE results with the experimental results of cold leg intermediate break LOCA obtained during ROSA-2/ LSTF test 7

Comparison of CATHARE results with the experimental results of cold leg intermediate break LOCA obtained during ROSA-2/ LSTF test 7

8 72 0

Sub-channel/system coupled code development and its application to SCWR-FQT loop

Sub-channel/system coupled code development and its application to SCWR-FQT loop

9 1 1

Verification of a real-time interactive transient simulator for Dalat nuclear research reactor

Verification of a real-time interactive transient simulator for Dalat nuclear research reactor

8 52 3

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