Progress With the International Pipe Failure Data Exchange Project

2007 ◽  
Author(s):  
Bengt Lydell ◽  
Alejandro Huerta ◽  
Karen Gott
Keyword(s):  
Nuclear Power ◽  
Data Exchange ◽  
Power Plants ◽  
Crack Depth ◽  
Pipe Failure ◽  
Energy Agency ◽  
Service Experience ◽  
Failure Data ◽  
Wall Thinning ◽  
Engineered Safeguards

Certain member countries of the Organisation for Economic Cooperation and Development (OECD) in 2002 established the OECD Pipe Failure Data Exchange Project (OPDE) to produce an international database on the piping service experience applicable to commercial nuclear power plants. OPDE is operated under the umbrella of the OECD Nuclear Energy Agency (NEA). The Project collects pipe failure data including service-induced wall thinning, part through-wall crack, pinhole leak, leak, and rupture/severance (i.e., events involving large leak rates up to and beyond the make-up capacity of engineered safeguards systems). The part through-wall events include degradation in excess of code allowable for pipe wall thinning or crack depth. OPDE also addresses such degradation that could have generic implications regarding the reliability of in-service inspection. At the end of 2006 the OPDE database included approximately 3,700 records on pipe failure affecting ASME Code Class 1 through 3 and non-Code piping. This paper summarizes the unique data quality considerations that are associated with the reporting and recording of piping component degradation and failure. The paper also summarizes the database content and puts it in perspective relative to past efforts to systematically collect and evaluate service experience data on piping performance.

Piping Service Life Experience in Commercial Nuclear Power Plants: Progress With the OECD Pipe Failure Data Exchange Project

2004 ◽  
Author(s):  
Bengt Lydell ◽  
Eric Mathet ◽  
Karen Gott
Keyword(s):  
Data Exchange ◽  
Power Plants ◽  
Nuclear Energy ◽  
Structural Integrity ◽  
Life Experience ◽  
Crack Depth ◽  
Pipe Failure ◽  
Energy Agency ◽  
Failure Data ◽  
Wall Thinning

An extension of a 1994–98 R&D project established in 2002 by certain member countries of the Organisation for Economic Cooperation (OECD), the OECD Pipe Failure Data Exchange (OPDE) Project has produced a major database on the piping service experience applicable to commercial nuclear plants. The 3-year project is operated under the umbrella of the OECD Nuclear Energy Agency (NEA) and organizations producing or regulating more than 80% of nuclear energy generation worldwide are contributing data to the OPDE Project. The Project considers pipe failure data including service-induced wall thinning, part through-wall crack, pinhole leak, leak, and rupture/severance (i.e., events involving large leak rates up to and beyond the make-up capacity of engineered safeguards systems). The part through-wall events include degradation in excess of code allowable for pipe wall thinning or crack depth. OPDE also addresses such degradation that could have generic implications regarding the reliability of in-service inspection. At the end of 2003 the OPDE database included approximately 4,400 records on pipe failure affecting ASME Code Class 1 through 3 and non-Code piping. The database also included an additional 450 records on water hammer events where the structural integrity of piping was challenged but did not fail. This paper summarizes the unique data quality considerations that are associated with piping components. The paper also summarizes the database content.

The OECD Pipe Failure Data Exchange Project: Data Validation on Canadian Plants

2004 ◽  
Author(s):  
Alexandre Colligan ◽  
Robert Lojk ◽  
Jovica Riznic
Keyword(s):  
Data Collection ◽  
Nuclear Power ◽  
Data Exchange ◽  
Power Plants ◽  
Data Validation ◽  
Pipe Failure ◽  
Energy Agency ◽  
Failure Data ◽  
Project Data ◽  
Project Objectives

The Nuclear Energy Agency (NEA) of the Organization for Economic Co-Operation and Development (OECD) has initiated a project to establish an international pipe failure data collection and exchange program. This OECD Pipe Failure Data Exchange (OPDE) Project has been established to encourage multilateral co-operation in the collection and analysis of data relating to pipe failure events in commercial nuclear power plants. This paper presents a brief description of the ODPE project objectives and work scope, as well as the Canadian contribution on data validation with respect to development and application of the pipe failure data collection on which OPDE is based.

The OECD Pipe Failure Data Exchange Project: Validation of Canadian Data

2006 ◽  
Author(s):  
Tom Viglaski ◽  
Andrei Blahoianu ◽  
Bengt Lydell ◽  
Jovica Riznic
Keyword(s):  
Data Collection ◽  
Nuclear Power ◽  
Data Exchange ◽  
Power Plants ◽  
Structural Integrity ◽  
Passive Component ◽  
Pipe Failure ◽  
Energy Agency ◽  
Failure Data ◽  
Project Objectives

Structural integrity of piping systems is important to plant safety and operability. Information on degradation and failure of piping components and systems is collected and evaluated by regulatory agencies, international organizations (e.g., OECD/NEA and IAEA) and industry organizations worldwide to establish systematic feedback to reactor regulation and research and development programs associated with non-destructive examination (NDE) technology, in-service inspection (ISI) programs, leak-before-break evaluations, risk-informed ISI, and probabilistic safety assessment (PSA) applications involving passive component reliability. In 2002, the Nuclear Energy Agency (NEA) of the Organization for Economic Co-Operation and Development (OECD) has initiated an international pipe failure data collection and exchange project. The OECD Pipe Failure Data Exchange (OPDE) Project has been established to encourage multilateral co-operation in the collection and analysis of data relating to pipe failure events in commercial nuclear power plants. At present, the database contains 3644 records to which twelve participating countries contributed. This paper presents a brief description of the ODPE project objectives and work scope, as well as the Canadian contribution on data validation with respect to development and application of the pipe failure data collection on which OPDE is based. It gives a number of tables and figures that can be obtained from these records, with selected data ranging from a very broad (i.e. level of participation in the database from each member country), to very specific (i.e. plant operational state at time of pipe failure discovery for CANDU reactors).

A Stochastic Model for Piping Failure Frequency Analysis Using OPDE Data

2009 ◽  
Vol 131 (5) ◽  
Author(s):  
X.-X. Yuan ◽  
M. D. Pandey ◽  
J. Riznic
Keyword(s):  
Nuclear Power ◽  
Process Model ◽  
Power Plants ◽  
Probabilistic Models ◽  
Accurate Estimation ◽  
Model Parameters ◽  
Pipe Failure ◽  
Failure Frequency ◽  
Failure Data ◽  
Class 1

The accurate estimation of piping failure frequency is an important task to support the probabilistic risk assessment and risk-informed in-service inspection of nuclear power plants. Although probabilistic models have been reported in the literature to analyze the piping failure frequency, this paper proposes a stochastic point process model that incorporates both a time dependent trend and plant-specific (or cohort) effects on the failure rate. A likelihood based statistical method is proposed for estimating the model parameters. A case study is presented to analyze the Class 1 pipe failure data given in the OPDE Database.

scholarly journals CANDU FIRE DATABASE

2019 ◽  
Vol 8 (2) ◽  
pp. 179-189 ◽  
Author(s):  
Hossam Shalabi ◽  
George Hadjisophocleous
Keyword(s):  
Risk Assessment ◽  
Time Series ◽  
Nuclear Power ◽  
Data Exchange ◽  
Power Plants ◽  
Nuclear Energy ◽  
Energy Agency ◽  
Candu Reactors ◽  
Weighting Factors ◽  
Future Potential

The Nuclear Energy Agency (NEA) is a specialized agency within the Organization for Economic Co-operation and Development (OECD). The International Fire Data Exchange Project (OECD FIRE) was designed by the NEA to encourage multilateral co-operation in the collection and analysis of data relating to fire events in nuclear power plants. We used Python advanced software to analyze the data related to CANDU reactor plants in Canada from the OECD FIRE Database, while providing weighting factors/percentage tables to be used in CANDU Fire probabilistic risk assessment analysis. We also used 5 different time-series methods to predict future potential fires in CANDU reactors, compared the results from different methods, and identified the best method to predict future fires in CANDU power plants.

OECD Pipe Failure Data Exchange Project (OPDE): 2003 Status Report

2004 ◽  
Author(s):  
Bengt Lydell ◽  
Eric Mathet ◽  
Karen Gott
Keyword(s):  
Data Exchange ◽  
Influence Factors ◽  
Status Report ◽  
First Year ◽  
Pipe Failure ◽  
Project Organization ◽  
Energy Agency ◽  
Reliability Parameters ◽  
Failure Data ◽  
Plant Operations

Established in 2002 as a three-year multilateral cooperation in the collection and analysis of data relating to pipe failure events, the OPDE project currently is supported by eighteen organizations from twelve member countries of the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD-NEA). Objectives of the OPDE are to collect and analyze pipe failure data to promote a better understanding of underlying causes of failure, observed and potential impact on plant operations and safety, and prevention. The data analysis includes characterization of pipe failure events by reliability attributes and influence factors to facilitate the estimation of piping reliability parameters. With emphasis on data validity and quality, during the first year of operation a coding format has been developed to ensure consistent interpretation and applications. This paper represents an abbreviated 2003 status report and an overview of the project organization and objectives.

Design and Analysis of a Reliable Communication System in Nuclear Safety Instrument & Control System

2021 ◽  
Author(s):  
Le Li ◽  
Zhihui Zhang ◽  
Chao Gao ◽  
Fei Zhou ◽  
Guangqiang Ma
Keyword(s):  
Communication Networks ◽  
Communication System ◽  
Communication Systems ◽  
Nuclear Power ◽  
Data Exchange ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Nuclear Safety ◽  
Safety Communication ◽  
Digital Control Systems

Abstract With the development of digital instrument and control technology for nuclear power plants in recent decades, communication networks have become an important part of safety digital control systems, which takes charge in data exchange between the various sub-systems, and extremely impact on the reliability and safety of the entire I&C system. Traditional communication systems where some special features, such as reliability, safety, real-time, certainty, and independence are not strictly required are various illustrated. However, how to implement a communication system in a safety I&C system is rarely stated in current research. In this research, a reliable safety communication system applied in nuclear power plants is designed and analyzed. The five key characteristics of nuclear safety communication networks are explained, followed by explanation of how to achieve these characteristics. The analysis and verification of the designed system are also stated in this paper, which contributes to proving that the designed nuclear safety communication system could applied in the nuclear power plants.

scholarly journals Study on Probabilistic Safety Goals for Multimodule High-Temperature Gas-Cooled Reactor Based on Chinese Societal Risks

2021 ◽  
Vol 2021 ◽  
pp. 1-10
Author(s):  
Jinghan Zhang ◽  
Jun Zhao ◽  
Jiejuan Tong
Keyword(s):  
High Temperature ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Regulatory Commission ◽  
Nuclear Safety ◽  
Energy Agency ◽  
Water Reactor ◽  
Regulatory Commission ◽  
High Temperature Gas ◽  
Probabilistic Safety

Nuclear safety goal is the basic standard for limiting the operational risks of nuclear power plants. The statistics of societal risks are the basis for nuclear safety goals. Core damage frequency (CDF) and large early release frequency (LERF) are typical probabilistic safety goals that are used in the regulation of water-cooled reactors currently. In fact, Chinese current probabilistic safety goals refer to the Nuclear Regulatory Commission (NRC) and the International Atomic Energy Agency (IAEA), and they are not based on Chinese societal risks. And the CDF and LERF proposed for water reactor are not suitable for high-temperature gas-cooled reactors (HTGR), because the design of HTGR is very different from that of water reactor. And current nuclear safety goals are established for single reactor rather than unit or site. Therefore, in this paper, the development of the safety goal of NRC was investigated firstly; then, the societal risks in China were investigated in order to establish the correlation between the probabilistic safety goal of multimodule HTGR and Chinese societal risks. In the end, some other matters about multireactor site were discussed in detail.

Load Factor for Evaluating Non-Planar Flaws in Carbon Steel Piping Using Limit Load Methodology

2016 ◽  
Author(s):  
Phuong H. Hoang
Keyword(s):  
Carbon Steel ◽  
Nuclear Power ◽  
Power Plants ◽  
Pipe Wall ◽  
Local Strain ◽  
Limit Load ◽  
Evaluation Methodology ◽  
Load Factor ◽  
Wall Thinning ◽  
Steel Piping

Non-planar flaw such as local wall thinning flaw is a major piping degradation in nuclear power plants. Hundreds of piping components are inspected and evaluated for pipe wall loss due to flow accelerated corrosion and microbiological corrosion during a typical scheduled refueling outage. The evaluation is typically based on the original code rules for design and construction, and so often that uniformly thin pipe cross section is conservatively assumed. Code Case N-597-2 of ASME B&PV, Section XI Code provides a simplified methodology for local pipe wall thinning evaluation to meet the construction Code requirements for pressure and moment loading. However, it is desirable to develop a methodology for evaluating non-planar flaws that consistent with the Section XI flaw evaluation methodology for operating plants. From the results of recent studies and experimental data, it is reasonable to suggest that the Section XI, Appendix C net section collapse load approach can be used for non-planar flaws in carbon steel piping with an appropriate load multiplier factor. Local strain at non-planar flaws in carbon steel piping may reach a strain instability prior to net section collapse. As load increase, necking starting at onset strain instability leads to crack initiation, coalescence and fracture. Thus, by limiting local strain to material onset strain instability, a load multiplier factor can be developed for evaluating non-planar flaws in carbon steel piping using limit load methodology. In this paper, onset strain instability, which is material strain at the ultimate stress from available tensile test data, is correlated with the material minimum specified elongation for developing a load factor of non-planar flaws in various carbon steel piping subjected to multiaxial loading.

Failure Probability Assessment of Piping Systems Affected by SCC and Pipe Wall Thinning for LBB Analysis

2011 ◽  
Author(s):  
Hiromasa Chitose ◽  
Hideo Machida ◽  
Itaru Saito
Keyword(s):  
Failure Probability ◽  
Nuclear Power ◽  
Power Plants ◽  
Pipe Wall ◽  
Probability Assessment ◽  
Wall Thinning ◽  
Piping Systems ◽  
Leak Before Break ◽  
Thinning Rate ◽  
Service Inspection

This paper provides failure probability assessment results for piping systems affected by stress corrosion cracking (SCC) and pipe wall thinning in nuclear power plants. On the basis of the results, considerations for applying the leak-before-break (LBB) concept in actual plants are presented. The failure probability for SCC satisfies the target failure probability even if conservative conditions are assumed. Moreover, for pipe wall thinning analysis, pre-service inspection is important for satisfying the target failure probability because the initial wall thickness affects the accuracy of the wall thinning rate. The pipe wall thinning analysis revealed that the failure probability is higher than the target probability if the bending stress in the pipe is large.

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