It is known from operation history of nuclear power plants (NPPs) that human factors considerations and human reliability analysis (HRA) are necessary for complete safety analysis of NPPs. HRA is usually performed to estimate the influence of human errors on the unavailability of various safety systems of NPPs;The objective of this work is to assess quantitatively the human contribution to the unavailability of those safety systems involved in the S(,2)C accident sequence. S(,2)C sequence is defined as a small loss of coolant accident (LOCA) and core meltdown after containment failure. This sequence is selected for this study because it makes a significant contribution to risk. In order to do that, gross operator error rates were estimated ...
For the reliability and safety of nuclear power plants (NPPs), their design and operation must follo...
The anticipated transient involving loss of offsite power has been identified as a major potential c...
ABSTRACT According to the incident/accident reports, unsuccessful implementation of steam generator ...
The role of human beings in the safe operation of a nuclear power plant has been a matter of concern...
This work investigates two important areas in human reliability engineering: models for human perfor...
A methodology is developed to identify and flag significant trends related to the safety and availab...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007...
In recent years, several advancements in nuclear power plant (NPP) probabilistic risk assessment (PR...
Advances in reactor designs, materials and human-machine interfaces guarantee safety and reliability...
This Master Thesis is framed within a collaboration agreement between the Nuclear Engineering Resear...
Probabilistic risk assessment (PRA) has become an important tool in the nuclear power industry, both...
The paper discusses work conducted to: (1) support the severe accident sequence analysis of a nuclea...
Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007...
More widespread use of digital technology is expected in the existing nuclear power plant main contr...
This paper describes the methodology used in a human reliability analysis (HRA) conducted during a q...
For the reliability and safety of nuclear power plants (NPPs), their design and operation must follo...
The anticipated transient involving loss of offsite power has been identified as a major potential c...
ABSTRACT According to the incident/accident reports, unsuccessful implementation of steam generator ...
The role of human beings in the safe operation of a nuclear power plant has been a matter of concern...
This work investigates two important areas in human reliability engineering: models for human perfor...
A methodology is developed to identify and flag significant trends related to the safety and availab...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007...
In recent years, several advancements in nuclear power plant (NPP) probabilistic risk assessment (PR...
Advances in reactor designs, materials and human-machine interfaces guarantee safety and reliability...
This Master Thesis is framed within a collaboration agreement between the Nuclear Engineering Resear...
Probabilistic risk assessment (PRA) has become an important tool in the nuclear power industry, both...
The paper discusses work conducted to: (1) support the severe accident sequence analysis of a nuclea...
Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007...
More widespread use of digital technology is expected in the existing nuclear power plant main contr...
This paper describes the methodology used in a human reliability analysis (HRA) conducted during a q...
For the reliability and safety of nuclear power plants (NPPs), their design and operation must follo...
The anticipated transient involving loss of offsite power has been identified as a major potential c...
ABSTRACT According to the incident/accident reports, unsuccessful implementation of steam generator ...