"Severe accident" trang 1 - tải miễn phí từ tailieunhanh
Severe accident issues raised by the fukushima accident and improvements suggested

Severe accident issues raised by the fukushima accident and improvements suggested
10    70    0
Prediction of the reactor vessel water level using fuzzy neural networks in severe accident circumstances of NPPS

Prediction of the reactor vessel water level using fuzzy neural networks in severe accident circumstances of NPPS
8    86    0
Overview of containment filtered vent under severe accident conditions at wolsong NPP unit 1

Overview of containment filtered vent under severe accident conditions at wolsong NPP unit 1
8    61    0
Analysis of flammability in the attached buildings to containment under severe accident conditions

Analysis of flammability in the attached buildings to containment under severe accident conditions
16    14    1
Analysis of in-vessel accident progression in VVER1000 NPP during SBO accident with external reactor vessel cooling method

Analysis of in-vessel accident progression in VVER1000 NPP during SBO accident with external reactor vessel cooling method
14    47    3
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3

Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3
12    12    1
Contribution of production and loss terms of fission products on incontainment activity under severe accident condition for VVER-1000

Contribution of production and loss terms of fission products on incontainment activity under severe accident condition for VVER-1000
13    67    0
Raim - A model for iodine behavior in containment under severe accident condition

Raim - A model for iodine behavior in containment under severe accident condition
11    76    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
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
Study on IVR strategy for VVER1000/V320 reactor in case of SBO accident

Study on IVR strategy for VVER1000/V320 reactor in case of SBO accident
15    18    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
Evaluation on in-vessel melt retention for VVER1000 reactor under SBO accident

Evaluation on in-vessel melt retention for VVER1000 reactor under SBO accident
16    11    1
A summary of fission-product-transport phenomena during SGTR severe accidents

A summary of fission-product-transport phenomena during SGTR severe accidents
10    12    1
Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions

Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions
14    8    1
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
Coronary artery endarterectomy during coronary artery bypass grafting - A solution for complete revascularization

Coronary artery endarterectomy during coronary artery bypass grafting - A solution for complete revascularization
6    39    1
Ruthenium transport in an RCS with airborne CsI

Ruthenium transport in an RCS with airborne CsI
11    10    1
PWR Medium Break LOCA source term analysis using ASTEC code

PWR Medium Break LOCA source term analysis using ASTEC code
13    15    1