Nuclear plant operating experience and several studies show that the risk from shutdown operation during Modes 4, 5, and 6 at pressurized water reactors and Modes 4 and 5 at boiling water reactors can be significant. This paper describes using the U.S. Nuclear Regulatory Commission’s full-power Standardized Plant Analysis Risk (SPAR) model as the starting point for development of risk evaluation models for commercial nuclear power plants. The shutdown models are integrated with their respective internal event at-power SPAR model. This is accomplished by combining the modified system fault trees from the SPAR full-power model with shutdown event tree logic. Preliminary human reliability analysis results indicate that risk is dominated by the...
It is known from operation history of nuclear power plants (NPPs) that human factors considerations ...
The Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute (EPRI) are support...
A systematic probabilistic safety assessment for a boiling water nuclear reactor core is performed u...
This is a preprint of a paper intended for publication in a journal or proceedings. Since changes ma...
Probabilistic risk assessments (PRAs) play an increasingly important role in the regulatory framewor...
In the past most probabilistic risk assessments (PRAs) of severe accidents in nuclear power plants h...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1999.Includes bi...
With the completion of the documentation of the results from the Grand Gulf Nuclear Power Plant Low ...
The U.S. Nuclear Regulatory Commission’s standardized plant analysis risk (SPAR) models are used to ...
NPP Goesgen developed a full-scope probabilistic risk assessment (PRA) model, allowing for an estima...
The U.S. Nuclear Regulatory Commission maintains a set of risk models covering the U.S. commercial n...
Many Probabilistic Safety Assessment (PSA) studies completed to the date demonstrated that the risk ...
The Standardized Plant Analysis Risk (SPAR) models are a set of probabilistic risk assessment (PRA) ...
Pričujoča magistrska naloga obravnava verjetnostne varnostne analize jedrske elektrarne v zaustavitv...
[[abstract]]Probabilistic safety assessment (PSA) uses a systematic approach to estimate the reliabi...
It is known from operation history of nuclear power plants (NPPs) that human factors considerations ...
The Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute (EPRI) are support...
A systematic probabilistic safety assessment for a boiling water nuclear reactor core is performed u...
This is a preprint of a paper intended for publication in a journal or proceedings. Since changes ma...
Probabilistic risk assessments (PRAs) play an increasingly important role in the regulatory framewor...
In the past most probabilistic risk assessments (PRAs) of severe accidents in nuclear power plants h...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1999.Includes bi...
With the completion of the documentation of the results from the Grand Gulf Nuclear Power Plant Low ...
The U.S. Nuclear Regulatory Commission’s standardized plant analysis risk (SPAR) models are used to ...
NPP Goesgen developed a full-scope probabilistic risk assessment (PRA) model, allowing for an estima...
The U.S. Nuclear Regulatory Commission maintains a set of risk models covering the U.S. commercial n...
Many Probabilistic Safety Assessment (PSA) studies completed to the date demonstrated that the risk ...
The Standardized Plant Analysis Risk (SPAR) models are a set of probabilistic risk assessment (PRA) ...
Pričujoča magistrska naloga obravnava verjetnostne varnostne analize jedrske elektrarne v zaustavitv...
[[abstract]]Probabilistic safety assessment (PSA) uses a systematic approach to estimate the reliabi...
It is known from operation history of nuclear power plants (NPPs) that human factors considerations ...
The Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute (EPRI) are support...
A systematic probabilistic safety assessment for a boiling water nuclear reactor core is performed u...