"nuclear accident" trang 2 - tải miễn phí từ tailieunhanh
Reactivity feedback effect on loss of flow accident in PWR

Reactivity feedback effect on loss of flow accident in PWR
12    67    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    86    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
Steam generator tube integrity analysis of a total loss of all heat sinks accident for wolsong NPP unit 1

Steam generator tube integrity analysis of a total loss of all heat sinks accident for wolsong NPP unit 1
8    96    0
Contribution to the study of fission products release from nuclear fuels in severe accident conditions: effect of the pO2 on Cs, Mo and Ba speciation

Contribution to the study of fission products release from nuclear fuels in severe accident conditions: effect of the pO2 on Cs, Mo and Ba speciation
10    54    0
Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes

Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes
9    70    0
Trends in severe accident research in Europe: SARNET network from Euratom to NUGENIA

Trends in severe accident research in Europe: SARNET network from Euratom to NUGENIA
10    62    0
Development of severe accident mitigation technology and analysis for SMART

Development of severe accident mitigation technology and analysis for SMART
8    8    1
An evaluation of volatile iodine in a pool under sever accident condition

An evaluation of volatile iodine in a pool under sever accident condition
9    15    1
Control of accidental discharge of radioactive materials by filtered containment venting system: A review

Control of accidental discharge of radioactive materials by filtered containment venting system: A review
12    66    0
Safety assurance through advances in long-term operation

Safety assurance through advances in long-term operation
7    60    0
Safety assessments and severe accidents, impact of external events on nuclear power plants and on mitigation strategies

Safety assessments and severe accidents, impact of external events on nuclear power plants and on mitigation strategies
9    95    0
Simulation of atmospheric radiocesium ( 137Cs) from Fukushima nuclear accident using FLEXPART-WRF driven by ERA5 reanalysis data

Simulation of atmospheric radiocesium ( 137Cs) from Fukushima nuclear accident using FLEXPART-WRF driven by ERA5 reanalysis data
12    57    3
Importance of continuing health care before emergency hospital evacuation: A fatal case of a hospitalized patient in a hospital within 5 km radius of Fukushima Daiichi Nuclear Power Plant: A case report

Importance of continuing health care before emergency hospital evacuation: A fatal case of a hospitalized patient in a hospital within 5 km radius of Fukushima Daiichi Nuclear Power Plant: A case report
6    1    1
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    7    1
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
Mechanical analysis of surface-coated zircaloy cladding

Mechanical analysis of surface-coated zircaloy cladding
13    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    616    0
Innovative Gen-II/III and research reactors’ fuels and materials

Innovative Gen-II/III and research reactors’ fuels and materials
7    106    0