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Owen Hedden
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Journal Articles
Journal:
Mechanical Engineering
Article Type: Select Article
Mechanical Engineering. May 2014, 136(05): 36–41.
Paper No: ME-14-MAY2
Published Online: May 1, 2014
Abstract
This article elaborates the evolution of code and standards for nuclear power plants. In the 1950s, need was felt for a revised set of design and fabrication rules to facilitate the development of safe, economically competitive water-cooled reactors contained in pressure vessels. These rules were codified in the first edition of the ASME Boiler and Pressure Vessel Code Section III, which was completed in 1963 and published in 1964. From the outset, both regulators and industry realized that the best way to develop many of the needed rules for the design, construction, and operation of nuclear facilities was the national standards consensus process. This process, followed by the American National Standards Institute and other recognized standards-issuing bodies such as ASME, brings together the expertise of individuals from government, industry, academia, and other stakeholders. In the years following the first publication of Section III, the coverage of the Code expanded to incorporate piping requirements, pressure-retaining components for pumps and valves, equipment and piping supports, reactor vessel internal structures, and other features of nuclear power plants.
Proceedings Papers
Steven L. McCracken, Steven M. Swilley, Yoshihisa Sekinuma, Owen Hedden, Dave Cowfer, Sampath Ranganath
Proc. ASME. PVP2011, Volume 1: Codes and Standards, 949-959, July 17–21, 2011
Paper No: PVP2011-57675
Abstract
Section III of the ASME Boiler and Pressure Vessel Code requires radiographic testing (RT) of pressure boundary welds. RT is performed to detect flaws that might be created in welds as they are fabricated. Current Section III acceptance standards require rejection and repair of flaw indications characterized as cracks, lack of fusion, or incomplete penetration regardless of the size of the indication or the structural significance of such indications on fitness for service (FFS). The current Section III requirements have been effective in meeting the design objective of preventing pressure boundary failures. However, the rules are sufficiently conservative that not only are structurally significant flaws excluded, but they also exclude more benign indications that have no impact on structural integrity. This approach has resulted in repairs for even minor flaws that have no FFS impact. In addition to the cost of performing these unnecessary repairs, the repairs may have contributed to service induced cracking because of the higher residual stresses from the repair. Clearly, there is a need to revisit the Section III inspection and repair rules so as to distinguish between structurally unacceptable flaws and benign flaws that have no FFS impact. This paper describes the technical basis for the proposed Section III Code Case that uses the FFS approach to eliminate the need for weld repairs for minor flaws that have been shown to have no structural impact. Specifically, the Code Case will provide the option to use qualified volumetric inspection to size the flaw indications accurately and define acceptance criteria to determine flaw sizes that are judged to have little structural significance. In addition to describing the requirements of the proposed Code Case, this paper also describes the technical basis for the flaw acceptance criteria and the results of ultrasonic (UT) qualification testing to demonstrate the capability to detect and characterize fabrication flaw indications.
eBook Chapter
Publisher: ASME Press
Published: 2012
ISBN: 9780791859872
Abstract
This chapter provides a chronological overview of the development of Section XI, “The Rules for Inservice Inspection of Nuclear Power Plant Components,” from its 1968 inception to the 1998 edition. It traces the development, edition-by-edition, of important Code elements including the philosophy behind many of the revisions. Emphasis is placed on the 1989 through 1998 editions because they apply to a majority of nuclear plants in the United States and in other countries. Through an extensive tabulation of Code Interpretations, this chapter also attempts to give the Code user some insights into clarification of many Section XI requirements. Further insight into the philosophy and technical basis behind Section XI may be gained from review of papers cited in the Bibliography of this chapter. Subsequent chapters of this book address the major areas of Section XI, including inservice inspection (ISI) examination and test programs, repairs and replacements, acceptance and evaluation criteria, containment programs, and fatigue crack growth. Reference to specific chapters is included as changes to their topics are introduced. Their specific discussions may be easier to follow and will be more complete than the brief chronological development in this chapter. Nondestructive examination is addressed in this chapter as its requirements evolve. The 2010 Edition of the Code including the 2011a Addenda provides the basis for canges and additions to this Chapter.
eBook Chapter
Publisher: ASME Press
Published: 2011
ISBN: 9780791859551
Abstract
In considering the future of nuclear power for electricity production in the U.S., it is necessary to consider the present public perception of nuclear power. It is also necessary to consider public perceptions of the various competing sources of electricity production. These include coal, natural gas, and the several “green” or “renewable” sources, including hydro, wind, and solar. Note that petroleum is no longer part of this discussion; its use has diminished to barely 1% of electricity production. Chapter 24 makes extensive use of referenced publications of the Nuclear Energy Institute, to take advantage of their expertise on specific subjects. This chapter also makes extensive use of referenced quotations from the works of established authors in the field to minimize misinterpretation of their work. In 1994, about the time that the last nuclear power plant was completed, USA Today announced [1]: “Essentially, the nation decided that nuclear power wasn't worth the price.” …“Nuclear energy provides only 21% of our electrical needs, 4% of our total energy consumption. Is it worth the trouble? Not until the problems of waste, safety and cost are completely resolved.”
eBook Chapter
Publisher: ASME Press
Published: 2009
ISBN: 9780791802700
Abstract
In Chapter 26, Owen F. Hedden provides an overview of the stipulations of Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components . A chronological overview of the development of Section XI is presented, from its inception in 1968 up to the 2004 Edition including 2006 Addenda. The chapter traces the development, Edition-by-Edition, of important elements of the Code, including the philosophy behind many of the revisions. Emphasis is placed on the 1989 through 2004 Editions, for they apply to the majority of plants in the United States and elsewhere. Through an extensive tabulation of Code Interpretations, this chapter also attempts to give the Code User some insight into clarification of many Section XI requirements. In the current revisions of Section XI, feedback from operating plants has resulted in new requirements to address stress corrosion cracking mechanisms, weld overlay piping repair techniques, and a program for risk-informed piping inspections. Owen notes that subsequent chapters of this book address the major areas of Section XI: in-service inspection examination and test programs, repairs and replacements, acceptance and evaluation criteria, containment programs, and fatigue crack growth. Nondestructive examination (NDE) is addressed in this chapter, as its requirements evolve. Owen mentions that Section XI initially had only 24 pages in 1970 but that it now has over 700 pages. Although originally it covered only light-water reactor Class 1 components and piping, now it includes Class 2 and Class 3 systems, metal and concrete containment, and liquid metalcooled reactor plants. With his association with Section XI Code Committee activities since their beginning, Owen is in a good posi-tion to comment on important areas that should not be overlooked as well as unimportant areas that should not distract attention.
eBook Chapter
Publisher: ASME Press
Published: 2006
ISBN-10: 0791802191
Abstract
In Chapter 26, Owen F. Hedden provides an overview of the stipulations of Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components. A chronological overview of the development of Section XI is presented, from its inception in 1968 up to the 1998 Edition. The chapter traces the development, Edition-by-Edition, of important elements of the Code, including the philosophy behind many of the revisions. Emphasis is placed on the 1989 through 2004 Editions, for they apply to the majority of plants in the United States and elsewhere. Through an extensive tabulation of Code Interpretations, this chapter also attempts to give the Code User some insight into clarification of many Section XI requirements. Owen notes that subsequent chapters of this book address the major areas of Section XI: inservice inspection examination and test programs, repairs and replacements, acceptance and evaluation criteria, containment programs, and fatigue crack growth. Nondestructive examination (NDE) is addressed in this chapter, as its requirements evolve. Owen mentions that Section XI initially had only 24 pages in 1970 but that it now has over 700 pages. Although originally it covered only light-water reactor Class 1 components and piping, now it includes Class 2 and Class 3 systems, metal and concrete containment, and liquid metal-cooled reactor plants. With his association with Section XI Code Committee activities since their beginning, Owen is in a good position to comment on important areas that should not be overlooked as well as unimportant areas that should not distract attention.
Journal Articles
Article Type: Technical Papers
J. Pressure Vessel Technol. August 2002, 124(3): 254–260.
Published Online: July 26, 2002
Abstract
This paper addresses implementation of ultrasonic (UT) process qualification by performance demonstration as imposed by the ASME Boiler and Pressure Vessel Code Section XI, Appendix VIII. The intended audience for the present paper is an engineer with a good knowledge of NDE, but a limited knowledge of the ASME Codes and Standards. The starting point for application of UT performance demonstration is described in a paper published in this journal just over a decade ago by Cowfer and Hedden. That paper addressed the application of ultrasonic performance demonstration to qualify an examination process for ASME Code Section XI inservice inspection. The present paper provides a brief summary of papers specifically selected to provide the reader with a concise update of progress in UT performance demonstration since the earlier paper. Given that qualification, the reader should not expect new information in this present paper. The papers selected have been mostly selected from those presented at ASME Pressure Vessels and Piping Conferences, from 1995 to 2002, addressing the subsequent development and application of the UT performance demonstration process. The emphasis is on work performed for nuclear utilities under the Performance Demonstration Initiative (PDI), for application to Section XI inservice inspection. However, material also is included describing parallel work in the European Community, and applications of UT performance demonstration in Sections I and VIII of the ASME Boiler and Pressure Vessel Code, for use of UT in place of RT for new construction, are included.
Journal Articles
Article Type: Technical Papers
J. Pressure Vessel Technol. August 2001, 123(3): 338–345.
Published Online: December 19, 2000
Abstract
In 1996, Code Case 2235, which allows ultrasonic examination of welds in lieu of radiography for ASME Section VIII Division 1 and Division 2 vessels, was approved by the ASME B&PV Code Committee. This Code Case has been revised to incorporate: 1) a reduction in minimum usable thickness from 4 ″ (107.6 mm) to 0.5 ″ (12.7 mm), and 2) flaw acceptance criteria including rules on multiple flaws. A linear elastic fracture mechanics procedure has been used in developing the flaw acceptance criteria. This paper presents the technical basis for Code Case 2235.