"Loss of Coolant Accident" trang 1 - tải miễn phí từ tailieunhanh
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    76    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    80    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    58    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    76    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    99    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    66    0
The impact of power coefficient of reactivity on candu 6 reactors

The impact of power coefficient of reactivity on candu 6 reactors
8    616    0
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    11    1
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    71    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    73    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    36    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    62    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    81    0
Infrared observation of ballooning and burst of nuclear fuel cladding tubes

Infrared observation of ballooning and burst of nuclear fuel cladding tubes
9    11    1
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    57    0