scholarly journals Limiting factor analysis of C-E nuclear plants. Volume 2, Part 2. Appendixes D-F. Final report

1979 ◽  
Author(s):  
E. Hewitt
Keyword(s):  
Factor Analysis ◽  
Limiting Factor ◽  
Final Report ◽  
Nuclear Plants

scholarly journals Limiting factor analysis of high availability nuclear plants. Final report

1979 ◽  
Author(s):  
V. Paggen ◽  
T. Patterson ◽  
D. James ◽  
T. Reddaway
Keyword(s):  
Factor Analysis ◽  
High Availability ◽  
Limiting Factor ◽  
Final Report ◽  
Nuclear Plants

The Impact of Probabilistic Modelling on Predicting the Remaining Life of Pipes in Nuclear Plants

2009 ◽  
Author(s):  
M. D. Pandey ◽  
D. Lu ◽  
D. Komljenovic
Keyword(s):  
End Of Life ◽  
Wall Thickness ◽  
Probabilistic Models ◽  
Structural Integrity ◽  
Life Cycle Management ◽  
Limiting Factor ◽  
Piping System ◽  
Practical Case ◽  
Nuclear Plants ◽  
The Impact

Flow accelerated corrosion (FAC) is a serious form of degradation in primary heat transport piping system (PHTS) of the nuclear reactor. Pipes transporting hot coolant from the reactor to steam generators are particularly vulnerable to FAC degradation, such as tight radius pipe bends with high flow velocity. FAC is a life limiting factor, as excessive degradation can result in the loss of structural integrity of the pipe. To prevent this, engineering codes and regulations have specified minimum wall thickness requirements to ensure fitness for service of the piping system. Nuclear utilities have implemented periodic wall thickness inspection programs and carried out replacement of pipes prior to reaching an unsafe state. To optimize the life cycle management of PHTS, accurate prediction of time of replacement or “end of life” of pipe sections is important. Since FAC is a time-dependent process of uncertain nature, the paper presents two probabilistic models for predicting the end of life. The paper illustrates that the modeling assumptions have a significant impact on the predicted number of replacements in the piping system. A practical case study is presented using wall thickness inspection data collected from Canadian nuclear plants.

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