Risk Informed In-Service-Inspection Activities of the ENIQ Task Group on Risk

2009 ◽  
Author(s):  
L. Gandossi ◽  
K. Simola ◽  
Adam Toft
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Structural Reliability ◽  
Task Group ◽  
Research Centre ◽  
European Level ◽  
Joint Research ◽  
European Nuclear ◽  
Service Inspection

The European Network for Inspection Qualification (ENIQ) was established in 1992 in response to increasing recognition of the importance of qualification of non-destructive inspection systems used in in-service inspection programmes for nuclear power plants. Driven by European Nuclear utilities and managed by the European Commission Joint Research Centre (JRC), ENIQ represents a network in which the available resources and expertise can be pooled at European level. ENIQ has recognized the importance of addressing, at European level, the issue of optimizing inspection strategies on the basis of risk by establishing a Task Group on Risk (TGR). Membership of TGR is drawn from European nuclear utilities and consultants. ENIQ TGR is focused on Risk-Informed In-Service Inspection (RI-ISI) methodologies. Its work is directed towards harmonisation in the field of codes, standards and best practice for RI-ISI methodologies, with the objective of increasing the safety of European nuclear power plants. In March 2005 TGR published a European Framework Document for RI-ISI. This publication provides guidance for both developing new RI-ISI approaches and using or adapting established approaches to a European environment, taking into account utility-specific characteristics and national regulatory requirements. More recently, ENIQ TGR has been working at producing more detailed recommended practices and discussion documents on several RI-ISI related issues, such as the role of ISI within the philosophy of defence-in-depth, the verification and validation of structural reliability models (SRMs) to be used in RI-ISI programmes, the use of expert panels and the applicability of RI-ISI to the reactor pressure vessel. Work is ongoing to develop a discussion document on updating of RI-ISI programmes, and new initiatives were launched to study topics such as what magnitude of risk reduction is reasonable to achieve through ISI, and how to set inspection targets, following the selection of ISI sites. In addition, TGR has been active in initiating international projects linked closely to its work, such as the JRC-OECD/NEA co-ordinated RI-ISI benchmark exercise (RISMET), and the project on the relation between inspection qualification and RI-ISI. This paper describes the key activities and publications of TGR to date.

2004 Edition of Japanese Fitness-for-Service Code for Nuclear Power Plants

2006 ◽  
Author(s):  
Koichi Kashima ◽  
Tomonori Nomura ◽  
Koji Koyama
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Pressure Vessels ◽  
Industrial Safety ◽  
National Rule ◽  
Class 1 ◽  
Asme Code ◽  
Service Inspection ◽  
Core Shroud

JSME (Japan Society of Mechanical Engineers) published the first edition of a FFS (Fitness-for-Service) Code for nuclear power plants in May 2000, which provided rules on flaw evaluation for Class 1 pressure vessels and piping, referring to the ASME Code Section XI. The second edition of the FFS Code was published in October 2002, to include rules on in-service inspection. Individual inspection rules were prescribed for specific structures, such as the Core Shroud and Shroud Support for BWR plants, in consideration of aging degradation by Stress Corrosion Cracking (SCC). Furthermore, JSME established the third edition of the FFS Code in December 2004, which was published in April 2005, and it included requirements on repair and replacement methods and extended the scope of specific inspection rules for structures other than the BWR Core Shroud and Shroud Support. Along with the efforts of the JSME on the development of the FFS Code, Nuclear and Industrial Safety Agency, the Japanese regulatory agency approved and endorsed the 2000 and 2002 editions of the FFS Code as the national rule, which has been in effect since October 2003. The endorsement for the 2004 edition of the FFS Code is now in the review process.

Evaluation and Numerical Simulation of Tsunami for Coastal Nuclear Power Plants of India

2006 ◽  
Author(s):  
Pavan K. Sharma ◽  
B. Ghosh ◽  
R. K. Singh ◽  
A. K. Ghosh ◽  
H. S. Kushwaha
Keyword(s):  
Early Warning ◽  
Early Warning System ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Warning System ◽  
Tsunami Source ◽  
Research Centre ◽  
Run Up ◽  
Three Phases

Recent tsunami generated on December 26, 2004 due to Sumatra earthquake of magnitude 9.3 resulted in inundation at the various coastal sites of India. The site selection and design of Indian nuclear power plants demand the evaluation of run up and the structural barriers for the coastal plants: Besides it is also desirable to evaluate the early warning system for tsunamigenic earthquakes. The tsunamis originate from submarine faults, underwater volcanic activities, sub-aerial landslides impinging on the sea and submarine landslides. In case of a submarine earthquake-induced tsunami the wave is generated in the fluid domain due to displacement of the seabed. There are three phases of tsunami: generation, propagation, and run-up. Reactor Safety Division (RSD) of Bhabha Atomic Research Centre (BARC), Trombay has initiated computational simulation for all the three phases of tsunami source generation, its propagation and finally run up evaluation for the protection of public life, property and various industrial infrastructures located on the coastal regions of India. These studies could be effectively utilized for design and implementation of early warning system for coastal region of the country apart from catering to the needs of Indian nuclear installations. This paper presents some results of tsunami waves based on different analytical/numerical approaches with shallow water wave theory.

Comparison of Nuclear Fitness for Service Codes: ASME Section XI and RSE-M AFCEN Codes

2014 ◽  
Author(s):  
Claude Faidy
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Light Water Reactors ◽  
Pressurized Water ◽  
Term Operation ◽  
Mechanical Components ◽  
Water Reactors ◽  
Test Requirements ◽  
Service Inspection

Two major Codes are used for Fitness for Service of Nuclear Power Plants: one is the ASME B&PV Code Section XI and the other one is the French RSE-M Code. Both of them are largely used in many countries, partially or totally. The last 2013 RSE-M covers “Mechanical Components of Pressurized Water Reactors (PWRs): - Pre-service and In-service inspection - Surveillance in operation or during shutdown - Flaw evaluation - Repairs-Replacements parts for plant in operation - Pressure tests The last 2013 ASME Section XI covers “Mechanical components and containment of Light Water Reactors (LWRs)” and has a larger scope with similar topics: more types of plants (PWR and Boiling Water Reactor-BWR), other components like metallic and concrete containments… The paper is a first comparison covering the scope, the jurisdiction, the general organization of each section, the major principles to develop In Service Inspection, Repair-Replacement activities, the flaw evaluation rules, the pressure test requirements, the surveillance procedures (monitoring…) and the connections with Design Codes… These Codes are extremely important for In-service inspection programs in particular and essential tools to justify long term operation of Nuclear Power Plants.

scholarly journals CONCEPTION OF REFERENCE BOOKS OF DEFECTS IS IN EQUIPMENT AND PIPELINES OF POWER AND TRANSPORT SYSTEMS

2020 ◽  
Vol 1 (46) ◽  
pp. 387-404
Author(s):  
Kharytonova L ◽  
◽  
Kutsenko O ◽  
Kadenko I ◽  
◽  
...  
Keyword(s):  
Finite Element Method ◽  
Finite Element ◽  
Power Systems ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Transport Systems ◽  
Object Of Study ◽  
Service Inspection ◽  
Element Method

The paper focuses on the one of the persperctive approaches to the increasing of thje safety of Nuclear Power Plants - Flaw Handbook Concept. Object of study - equipment and piping of Nuclear Power Plants. Purpose of study - the description of the Flaw Handbook Concept and the application of the concept for the specific example. Method of the study - numerical procedures of the finite-element method and fracture mechanics. In the modern economics the optimization of the performance and operation of industry and power systems is of the main importance. The Flaw Handbook Concept is considered in the paper. This concept is applied on the nuclear power plants in the leading states with the aim of the optimization of the procedures of in-service inspection and repair. The main steps of the concept are considered and applied for the specific example. An example of Flaw Handbook using is analysed. The results of the paper can be incorporated into the procedures of in-service inspection for the safety-significant equipment and piping. KEYWORDS: FLAW HANDBOOK, BRITTLE FRACTURE, FATIGUE, FINITE-ELEMENT METHOD, SURGE PIPE.

NULIFE: European Network Dedicated to Nuclear Plant Life Management

2007 ◽  
Author(s):  
Rauno Rintamaa ◽  
Irina Aho-Mantila ◽  
Nigel Taylor
Keyword(s):  
Life Prediction ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Nuclear Plant ◽  
Research Centre ◽  
European Network ◽  
Factors Affecting ◽  
Plant Life ◽  
Common Understanding

The European Network of Excellence NULIFE (Nuclear Plant Life Prediction) has been launched with a clear focus on integrating safety-oriented research on materials, structures and systems and exploiting the results of this integration through the production of harmonised lifetime assessment methods. NULIFE will help provide a better common understanding of, and information on, the factors affecting the lifetime of nuclear power plants which, together with associated management methods, will help facilitate extensions to the safe and economic lifetime of existing nuclear power plants. In addition, NULIFE will help in the development of design criteria for future generations of nuclear power plant. Led by VTT (Technical Research Centre of Finland), the five-year project has a total budget in excess of EUR 8 millions, with partners drawn from leading research institutions, technical support organisations, power companies and manufacturers throughout Europe.

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