In the past most probabilistic risk assessments (PRAs) of severe accidents in nuclear power plants have considered initiating events which could potentially lead to core damage and containment failure during normal full power operation. However, recent studies and operational experience during periods while plants were shutdown for maintenance or refueling indicated that potential accidents initiated during low power operation or shutdown conditions could also potentially become important contributors to risk. In 1989, the Nuclear Regulatory Commission (NRC) began an extensive program to assess the risk during low power and shutdown operation. Two plants, Surry (a pressurized water reactor, PWR) and Grand Gulf (a boiling water reactor ,BWR)...
After the occurrence of several significant events in nuclear power plants during shutdown modes of ...
[[abstract]]Probabilistic safety assessment (PSA) uses a systematic approach to estimate the reliabi...
One of the important issues raised from the Fukushima-Daiichi accident is the safety of multi-unit s...
The objectives are to assess the risks of severe accidents initiated during plant operational states...
To gain a better understanding of the risk significance of low power and shutdown modes of operation...
During 1989 the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully exam...
This document contains a summarization of the results and insights from the Level 1 accident sequenc...
During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully exa...
With the completion of the documentation of the results from the Grand Gulf Nuclear Power Plant Low ...
Nuclear plant operating experience and several studies show that the risk from shutdown operation du...
The long-term availability of less expensive power and the increasing plant modification and mainten...
Operation of pressurised water reactors involves shutdown periods for refuelling and maintenance. In...
Beginning in 1997, risk assessment was performed for each Advanced Test Reactor (ATR) outage aiding ...
As part of the Nondestructive Evaluation Reliability Program sponsored by the US Nuclear Regulatory ...
[[abstract]]The core damage frequency caused by loss of residual heat removal (RHR) events was asses...
After the occurrence of several significant events in nuclear power plants during shutdown modes of ...
[[abstract]]Probabilistic safety assessment (PSA) uses a systematic approach to estimate the reliabi...
One of the important issues raised from the Fukushima-Daiichi accident is the safety of multi-unit s...
The objectives are to assess the risks of severe accidents initiated during plant operational states...
To gain a better understanding of the risk significance of low power and shutdown modes of operation...
During 1989 the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully exam...
This document contains a summarization of the results and insights from the Level 1 accident sequenc...
During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully exa...
With the completion of the documentation of the results from the Grand Gulf Nuclear Power Plant Low ...
Nuclear plant operating experience and several studies show that the risk from shutdown operation du...
The long-term availability of less expensive power and the increasing plant modification and mainten...
Operation of pressurised water reactors involves shutdown periods for refuelling and maintenance. In...
Beginning in 1997, risk assessment was performed for each Advanced Test Reactor (ATR) outage aiding ...
As part of the Nondestructive Evaluation Reliability Program sponsored by the US Nuclear Regulatory ...
[[abstract]]The core damage frequency caused by loss of residual heat removal (RHR) events was asses...
After the occurrence of several significant events in nuclear power plants during shutdown modes of ...
[[abstract]]Probabilistic safety assessment (PSA) uses a systematic approach to estimate the reliabi...
One of the important issues raised from the Fukushima-Daiichi accident is the safety of multi-unit s...