scholarly journals State-of-practice review of ultrasonic in-service inspection of Class I system piping in commercial nuclear power plants

1982 ◽  
Author(s):  
C.J. Morris ◽  
F.L. Becker
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Class I ◽  
Practice Review ◽  
State Of Practice ◽  
Service Inspection

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.

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.

RSE-M Nuclear In-Service Inspection Code New Flaw Interaction Rules

2017 ◽  
Author(s):  
Claude Faidy
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Multiple Defects ◽  
The World ◽  
Service Inspection

After a quick overview of RSE-M scope now used on more than 100 Nuclear Power Plants in the World, this paper will present the flaw evaluation rules of RSE-M Appendix 5. This Appendix considers cracks, volumetric defects and thinning areas. Periodically updated on a yearly bases, the rules cover cracks in different components, for different material, in different location. It consider defects interaction in Appendix 5 - Chapter 5-1. In the case of multiple defects, after determining the dimensions for each defect according to the rules in previous chapters, the non-interaction conditions between the elementary defects given shall be checked. If these conditions are not met, the defects shall be grouped according to a dedicated chapter. This review is done on the basis of RSE-M 2015 edition and last modifications of 2016 edition.

Development of Database for the In-Service Inspection of the Concrete Structures of the Finnish Nuclear Power Plants

2013 ◽  
Vol 100 (4) ◽  
pp. 226-233 ◽  
Author(s):  
Fahim Al-Neshawy ◽  
Jukka Piironen ◽  
Esko Sistonen ◽  
Erkki Vesikari ◽  
Miguel Ferreira
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Concrete Structures ◽  
Service Inspection

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.

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