Overview of the ASME Section XI Code Relating to NDE and Ultrasonic Examination Performance Demonstration

1991 ◽  
Vol 113 (2) ◽  
pp. 170-173 ◽  
Author(s):  
C. D. Cowfer ◽  
O. F. Hedden
Keyword(s):  
Pressure Vessel ◽  
Probability Of Detection ◽  
Examination System ◽  
Fitness For Duty ◽  
Nondestructive Examination ◽  
Ultrasonic Examination ◽  
Examination Performance ◽  
Flaw Sizing ◽  
Performance Demonstration ◽  
Service Inspection

Nondestructive examination (NDE) in Section XI of the ASME Boiler and Pressure Vessel Code has been an evolving process. The Code’s use of NDE for in-service inspection (ISI) to establish fitness for duty has brought about major changes in applied NDE philosophy and practice. The publication in Section XI, 1989 Addenda, of mandatory Appendix VIII, “Performance Demonstration for Ultrasonic Examination System,” sets a precedent for both NDE performance and recognition of the total NDE system (personnel, equipment and procedures). This paper highlights appropriate portions of Appendix VIII. Performance values such as probability of detection (POD) and flaw sizing accuracy are addressed. The use of flawed specimens for performance demonstration qualifies personnel, equipment and procedures, hence the “Ultrasonic System” qualification. Appendix VIII provides the opportunity for technique performance demonstration for assessment of material aging and qualification of components and systems for continued service. This article provides the background and justification for Code action to publish Appendix VIII.

Expanded Influence of UT Performance Demonstration and Fitness-for-Service Analysis in the Nuclear Power Industry

2011 ◽  
Author(s):  
Owen F. Hedden ◽  
C. David Cowfer
Keyword(s):  
Structural Analysis ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Pressure Vessel ◽  
Nuclear Power ◽  
Probability Of Detection ◽  
Nuclear Power Industry ◽  
Nondestructive Examination ◽  
Performance Demonstration ◽  
Plant Components

This paper addresses recent development and application of ASME Boiler and Pressure Vessel Code and Code Case requirements for weld nondestructive examination (NDE) and for fitness-for-service (FFS) structural analysis of the flaws thus discovered. A brief description of the basis for this development is included. Reviews are presented of additions to the literature addressing applications to nuclear power plant components. Issues regarding application of Code Cases 2235 and N-529 are presented. Concerns regarding the importance of reliable probability of detection (POD) data for different weld categories are addressed. Concerns with appropriate acceptance standards for flaws in different weld categories and materials are also addressed.

Qualification of Ultrasonic Examination for RPV Nozzle to Shell Welds of EPR Nuclear Power Plant

2017 ◽  
Author(s):  
WeiQiang Wang ◽  
Zhe Yu ◽  
Xin Ye ◽  
HuaiDong Chen ◽  
GuanBing Ma
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Pressure Vessel ◽  
Nuclear Power ◽  
Ultrasonic Inspection ◽  
Primary Circuit ◽  
Ultrasonic Examination ◽  
Under Construction ◽  
Technical Solutions ◽  
Service Inspection

European Pressurized Reactor (EPR) nuclear power plant is now under construction in China. One of the biggest changes in the EPR reactor pressure vessel (RPV) is the nozzle to shell welds are designed as “set-on” principle instead of “set-in” principle in the CPR1000 units. The nozzle to shell welds of the EPR pressure vessel must be inspected according to the RSE-M code. This is necessary in order to guarantee the integrity of the primary circuit. The In-Service Inspection (ISI) program of EPR nuclear power plant demands the automatic ultrasonic inspection of the nozzle to shell welds from nozzle inner surface. This paper presents the technical characteristics of the EPR reactor vessel, and analyzes the in-service examination requirements of nozzle to shell welds. Technical solutions have been designed to perform the examination of the component. The qualification process of the ultrasonic examination of the nozzle to shell welds is also presented.

Flamanville 3 EPR: How to Define the Pre-Service NDE Inspection Program

2010 ◽  
Author(s):  
F. Champigny ◽  
P. Blin ◽  
J. L. Guilloteau
Keyword(s):  
Structural Integrity ◽  
Secondary Systems ◽  
Main Components ◽  
First Time ◽  
Performance Demonstration ◽  
Service Inspection ◽  
Fast Fracture

The last generation of PWR, the European Pressurizer Reactor, is being built both in Finland at Olkiluoto and in France at Flamanville where it will be the second unit in operation in two years. The conception of the reactor has no fundamental differences compared with the last French and German generations (i.e. N4 1450 MW and KONVOI 1300 MW). In fact the EPR is a synthesis of the best knowledge from both parts of Rhin river. Nevertheless, for what concerns the primary and secondary systems, few new issues have been implemented and they have important consequences for the pre-service inspection programme. First of it, main coolant lines and main components are declared break preclusion that means another approach for the in-service inspection and the requirements for pre-service inspection. A second one, is that the 1999 ministerial order will apply for the first time on a new unit. The inspection programme has to take it into account particularly in terms of NDE performance demonstration. In terms of structural integrity, the most important areas have been reviewed with fast fracture and fatigue criteria to determine the levels of NDE qualifications. This paper describes the important steps to reach the PSI and what is being developed in terms of NDE in relation to the structural integrity. Several examples are given to illustrate how EDF prepares the PSI of the EPR.

Ultrasonic Inspection of Dissimilar Metal Welds for Probabilistic Reliability Assessment of Pipe Welds

2017 ◽  
Author(s):  
Sandra Dugan ◽  
Anne Jüngert
Keyword(s):  
Material Properties ◽  
Ultrasonic Inspection ◽  
Probability Of Detection ◽  
Grain Structure ◽  
Simple Relationship ◽  
Dissimilar Metal ◽  
Flaw Sizing ◽  
Safety Research ◽  
Lifetime Analysis ◽  
Ultrasonic Propagation

There are several sources of uncertainties which need to be considered in a probabilistic reliability and lifetime assessment of safety-relevant components. In addition to the probabilistic distribution of material properties, the size and properties of flaws present in a component contribute to uncertainties in the lifetime analysis. In a current reactor safety research project, a methodology for a probabilistic fracture mechanics assessment of reliability for components with austenitic and dissimilar metal welds will be developed using the combined results from statistical evaluation of material properties and ultrasonic inspection (UT). Dissimilar metal welds present a particular challenge for ultrasonic testing due to the effects of the material anisotropy on ultrasonic propagation and scattering. Evaluation of inspection results is typically done using image-based techniques. As there is no simple relationship between UT response and flaw size, criteria for image evaluation and flaw sizing have to be defined taking into account the influence of various factors such as material and flaw properties on the UT response. In this paper, we present results from a study of the influence of grain structure on the ultrasonic inspection results and discuss the challenges of extracting data for probability of detection (POD) analyses.

scholarly journals An Ability to Adapt and Change

2014 ◽  
Vol 136 (11) ◽  
pp. 36-37
Author(s):  
Madiha El Mehelmy Kotb
Keyword(s):  
Life Cycle ◽  
Pressure Vessel ◽  
Pressure Vessels ◽  
Electronic Format ◽  
The World ◽  
Regulatory Approach ◽  
Section Viii ◽  
Division 2 ◽  
Service Inspection ◽  
Technical Services

This article reviews about the views of Madiha El Mehelmy Hotb, the Head of the Pressure Vessels Technical Services Division for Regie Du Batiment Du Quedec, on how ASME Boiler and Pressure Vessel Code has evolved over the years. Hotb reveals that during the 1980s, ASME’s regulatory approach covered all aspects of the life cycle of a boiler or a pressure vessel from design to being taken out of service. It also confirmed every step in between – fabrication, installation, repair and modification, and in-service inspection. During later years, the institution moved toward accreditation of authorized inspection agencies, changed the publication cycle from three years to two, eliminated addenda, and restructured the Code committees. New Section VIII and division 2 were written, and the Codes were published in digital electronic format. Hotb believes that the Code will continue to be widely used and adopted in future. It will have a bigger and larger input from all over the world and will have further outreach and adoption by far more countries.

Sign in / Sign up

Export Citation Format

Share Document