Loss of coolant accident trang 1 tải miễn phí từ TAILIEUCHUNG

"Loss of coolant accident" trang 1 - tải miễn phí từ Tailieuchung

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 62 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 72 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 47 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 59 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 80 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 52 0

The impact of power coefficient of reactivity on candu 6 reactors

The impact of power coefficient of reactivity on candu 6 reactors

8 70 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 1 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 56 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 65 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 31 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 54 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 72 0

Infrared observation of ballooning and burst of nuclear fuel cladding tubes

Infrared observation of ballooning and burst of nuclear fuel cladding tubes

9 1 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 44 0

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