Sensitivity analysis of input parameters for pressure tube integrity evaluation

Kwak, Sang-Log; Lee, Joon-Seong; Kim, Young‐Jin; Park, Youn-Won

doi:10.1016/j.nucengdes.2005.05.008

Cited by 7 publications

(2 citation statements)

References 11 publications

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“…A cornerstone of this activity is thorough inspection during planned statutory outages. In CANDU (Canada Deuterium-Uranium) reactors a representative subset of the fuel channels, usually around 20 out of 400, are subject to detailed regular inspection (Kwak et al, 2005) with each reactor inspected at least once every three years. The selection of these channels is governed by a number of factors, such as the desire to revisit a channel that has been previously inspected, targeting channels exhibiting unusual behaviours as indicated by online monitoring, and the need to have a representative subset of the full core.…”

Section: Candu Reactor Inspectionmentioning

confidence: 99%

Automated sizing and classification of defects in CANDU pressure tubes

Lardner¹,

West²,

Dobie³

et al. 2017

Nuclear Engineering and Design

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Pressure tubes within CANDU reactors are subject to frequent ultrasonic non-destructive examination to identify and characterize any defects that pose a risk of initiating Delayed Hydride Cracking (DHC), a well-known problem that occurs in zirconium components that are subject to high mechanical and thermal stresses. The analysis of the ultrasonic data gathered from the pressure tubes is often a long and repetitive process on the critical path to the restart of the reactor. Motivations for developing an automated system include saving time on the critical path, minimising human subjectivity from the process and increasing repeatability of measurements. An automated system providing decision support to analysts also reduces the risk of operator fatigue by minimising time spent processing routine defects. This paper describes a novel system for the automated analysis of CANDU pressure tube inspection data. The system automates the entire initial examination process including the complex decision-making procedures by implementing an expert system with an associated rule-base. Results from this system are detailed, illustrating the location and characterisation of defects and key features within the pressure tube with a high degree of accuracy while increasing repeatability through the removal of subjectivity in measurements.

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Section: Candu Reactor Inspectionmentioning

confidence: 99%

Automated sizing and classification of defects in CANDU pressure tubes

Lardner¹,

West²,

Dobie³

et al. 2017

Nuclear Engineering and Design

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show abstract

“…Sensitivity analysis of input parameters may be used as a guide to the most economic deployment of resources on maintenance, inspection and repair [7,8]. So the probabilistic approach is obviously the best choice in practical applications when sufficient information on the distribution of the random variables is known [9][10][11].…”

Section: Introductionmentioning

confidence: 99%

Sensitivity Analysis for the Cylindrical Pressure Vessel of 16MnR Steel with the Monte-Carlo Method

Zhang

2011

MSF

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Probabilistic safety assessment procedure is used to evaluate the cylindrical pressure vessel of 16MnR steel, which regards defect sizes, mechanical properties and stresses as random variables. Monte-Carlo simulation is applied on calculating failure probability, which is based on the Chinese safety assessment procedure (GB/T 19624-2004). Sensitivity analysis is performed to estimate the effect of change in input parameters. The results show that failure probability may be influenced significantly by change in parameters concerning yield strength and film stress. Additionally, the different distributions of input parameters have an effect on failure probability.

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Development of a web-based aging monitoring system for an integrity evaluation of the major components in a nuclear power plant

Choi

Yeum

et al. 2010

International Journal of Pressure Vessels and Piping

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Sensitivity analysis of input parameters for pressure tube integrity evaluation

Cited by 7 publications

References 11 publications

Automated sizing and classification of defects in CANDU pressure tubes

Automated sizing and classification of defects in CANDU pressure tubes

Sensitivity Analysis for the Cylindrical Pressure Vessel of 16MnR Steel with the Monte-Carlo Method

Development of a web-based aging monitoring system for an integrity evaluation of the major components in a nuclear power plant

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