Study on the Methods and Possibilities of Probabilistic Fracture Mechanics Based on Data for the Steel Containment of a Nuclear Power Plant

1984 ◽  
pp. 547-558
Author(s):  
A. Bruckner ◽  
R. Haberer ◽  
D. Munz
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Fracture Mechanics ◽  
Nuclear Power ◽  
Probabilistic Fracture Mechanics

Application of Probabilistic Fracture Mechanics Analysis on BWR Recirculation Piping Systems

2016 ◽  
Author(s):  
Yu-Yu Shen ◽  
Hsoung-Wei Chou ◽  
Chin-Cheng Huang ◽  
Ru-Feng Liu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Fracture Mechanics ◽  
Nuclear Power ◽  
Fracture Probability ◽  
Probability Of Detection ◽  
Piping System ◽  
Probabilistic Fracture Mechanics ◽  
Piping Systems ◽  
Inspection And Maintenance

In recent years, the probabilistic fracture mechanics (PFM) approach has been widely applied to estimate the fracture risk of nuclear power plant piping systems. In the paper, the probabilistic fracture mechanics code, PRO-LOCA, developed by the Probabilistic Analysis as a Regulatory Tool for Risk Informed Decision Guidance (PARTRIDGE) project, is employed to practically evaluate the fracture probability of the recirculation piping system welds in a Taiwan domestic boiling water reactor (BWR) nuclear power plant. To begin with, the models based on the real situation of the recirculation piping welds are built. Then, the probabilities of through-wall cracking, leak with different rates, and rupture on the welds considering both in-service inspection and leak detection are analyzed. Meanwhile, the effects of probability of detection curves of ISI on the piping are simulated. Further, the efficiencies of performing the induction heating stress improvement and weld overlay are also studied and discussed. The present work could provide a reference of operation, inspection and maintenance for BWR plants in Taiwan.

Risk Based Inspection Pilot Study of Ignalina Nuclear Power Plant, Unit 2

2002 ◽  
Author(s):  
Bjorn Brickstad ◽  
Adam Letzter ◽  
Arturas Klimasauskas ◽  
Robertas Alzbutas ◽  
Linas Nedzinskas ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Pilot Study ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Fracture Mechanics ◽  
Nuclear Power ◽  
Damage Mechanism ◽  
Core Damage ◽  
Steel Welds ◽  
Nuclear Power Plant Unit

A project with the acronym IRBIS (Ignalina Risk Based Inspection pilot Study) has been performed with the objective to perform a quantitative risk analysis of a total of 1240 stainless steel welds in Ignalina Nuclear Power Plant, unit 2 (INPP-2). The damage mechanism is IGSCC and the failure probabilities are quantified by using probabilistic fracture mechanics. The conditional core damage probabilities are taken from the plant PSA.

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