"Coolant accident" trang 1 - tải miễn phí từ tailieuXANH
Investigation of a hydrogen mitigation system during large break loss of coolant accident for a two-loop pressurized water reactor

Investigation of a hydrogen mitigation system during large break loss of coolant accident for a two-loop pressurized water reactor
10    79    0
Simulation of containment pressurization in a large break-loss of coolant accident using singlecell and multicell models and contain code

Simulation of containment pressurization in a large break-loss of coolant accident using singlecell and multicell models and contain code
14    50    0
Effect of emergency core cooling system flow reduction on channel temperature during recirculation phase of large break loss-of-coolant accident at Wolsong unit 1

Effect of emergency core cooling system flow reduction on channel temperature during recirculation phase of large break loss-of-coolant accident at Wolsong unit 1
10    36    0
Assessment of radioactive gaseous effluent released from nuclear power plant Ninh Thuan 1 under scenario of ines-level 5 nuclear accident

Assessment of radioactive gaseous effluent released from nuclear power plant Ninh Thuan 1 under scenario of ines-level 5 nuclear accident
9    54    0
Assessment of radioactive gaseous effluent released from Ninh Thuan 1 nuclear power plant under scenario of ines-level 7 nuclear accident

Assessment of radioactive gaseous effluent released from Ninh Thuan 1 nuclear power plant under scenario of ines-level 7 nuclear accident
7    106    0
Performance analysis of the passive safety features of iPOWER under Fukushima-like accident conditions

Performance analysis of the passive safety features of iPOWER under Fukushima-like accident conditions
7    55    0
Evaluations of Mo-alloy for light water reactor fuel cladding to enhance accident tolerance

Evaluations of Mo-alloy for light water reactor fuel cladding to enhance accident tolerance
6    71    0
Risk of Japanese PWR plants by shutting off forced core cooling in an accident requiring safety injection system

Risk of Japanese PWR plants by shutting off forced core cooling in an accident requiring safety injection system
6    8    2
Application of the conservative and best estimate plus uncertainty approach to analysis of LB-loca accident for VVER-1200/491 reactor using relap 5

Application of the conservative and best estimate plus uncertainty approach to analysis of LB-loca accident for VVER-1200/491 reactor using relap 5
10    7    2
Uncertainty analysis of ROSA/LSTF test by RELAP5 code and PKL counterpart test concerning PWR hot leg break LOCAs

Uncertainty analysis of ROSA/LSTF test by RELAP5 code and PKL counterpart test concerning PWR hot leg break LOCAs
13    57    0
The impact of power coefficient of reactivity on candu 6 reactors

The impact of power coefficient of reactivity on candu 6 reactors
8    61    0
Oxygen segregation in pre-hydrided Zircaloy-4 cladding during a simulated LOCA transient

Oxygen segregation in pre-hydrided Zircaloy-4 cladding during a simulated LOCA transient
8    72    0
A study of different cases of VVER reactor core flooding in a large break loss of coolant accident

A study of different cases of VVER reactor core flooding in a large break loss of coolant accident
11    207    0
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    51    0
An attempt for a unified description of mechanical testing on Zircaloy-4 cladding subjected to simulated LOCA transient

An attempt for a unified description of mechanical testing on Zircaloy-4 cladding subjected to simulated LOCA transient
9    78    0
Melt jet-breakup and fragmentation phenomena in nuclear reactors: A review of experimental works and solidification effects

Melt jet-breakup and fragmentation phenomena in nuclear reactors: A review of experimental works and solidification effects
16    10    1
Infrared observation of ballooning and burst of nuclear fuel cladding tubes

Infrared observation of ballooning and burst of nuclear fuel cladding tubes
9    4    2
Prediction of hydrogen concentration in containment during severe accidents using fuzzy neural network

Prediction of hydrogen concentration in containment during severe accidents using fuzzy neural network
9    54    0
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