"Accident analysis" trang 1 - tải miễn phí từ tailieunhanh
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
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
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
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
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
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
Preliminary accident analysis of Flexblue® underwater reactor

Preliminary accident analysis of Flexblue® underwater reactor
10    84    0
Development of severe accident mitigation technology and analysis for SMART

Development of severe accident mitigation technology and analysis for SMART
8    8    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
Using threshold analysis to assess the robustness of public health intervention recommendations from network meta-analyses: Application to accident prevention in households with children under five

Using threshold analysis to assess the robustness of public health intervention recommendations from network meta-analyses: Application to accident prevention in households with children under five
13    22    1
Accident Precursor Analysis And Management

Accident Precursor Analysis And Management
40    49    0
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
Evaluation of occupational accidents in forestry in Europe and Turkey by k-means clustering analysis

Evaluation of occupational accidents in forestry in Europe and Turkey by k-means clustering analysis
15    37    3
Situation awareness errors in anesthesia and critical care in 200 cases of a critical incident reporting system

Situation awareness errors in anesthesia and critical care in 200 cases of a critical incident reporting system
10    20    1
Data Mining technique: Application of Apriori algorithm for road accident analysis

Data Mining technique: Application of Apriori algorithm for road accident analysis
9    22    1
Detailed neutronic study of the power evolution for the European Sodium Fast Reactor during a positive insertion of reactivity

Detailed neutronic study of the power evolution for the European Sodium Fast Reactor during a positive insertion of reactivity
9    8    1
BANK TRENDS: Analysis of Emerging Risks In Banking

BANK TRENDS: Analysis of Emerging Risks In Banking
11    63    0
PWR Medium Break LOCA source term analysis using ASTEC code

PWR Medium Break LOCA source term analysis using ASTEC code
13    15    1
Multi-physics models for design basis accident analysis of sodium fast reactors. Part I: Validation of three-dimensional TRACE thermal-hydraulics model using Phenix end-of-life experiments

Multi-physics models for design basis accident analysis of sodium fast reactors. Part I: Validation of three-dimensional TRACE thermal-hydraulics model using Phenix end-of-life experiments
11    13    1