Continuing & Changing Priorities of ASME Boiler & Pressure Vessel Codes and StandardsEDITORK. R. RAO

Continuing & Changing Priorities of ASME Boiler & Pressure Vessel Codes and Standards
EDITOR
K. R. RAO

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Library of Congress Cataloging-in-Publication Data
Rao, K. R., 1933-
Continuing & changing priorities of ASME boiler & pressure vessel codes and standards / K.R. Rao. pages cm
Revision of volume 3 of the Companion guide to the ASME boiler & pressure vessel code. Includes bibliographical references and index.
ISBN 978-0-7918-6019-9 (alk. paper)
1. Steam-boilers—Standards. 2. Pressure vessels—Standards. I. American Society of Mechanical Engineers. Boiler and Pressure Vessel Committee. ASME boiler and pressure vessel code. II. Companion guide to the ASME boiler & pressure vessel code. III. Title.

 
(Source: “100 Years The ASME Boiler and Pressure Vessel Code”, by Gerry Eisenberg, p. 25, Winter, 2014 National Board Bulletin, National Board.org.)
CONTENTS
Dedication	iii
Acknowledgements	v
Contributor Biographies	vii
Preface	xxxi
Introduction	xxxvii
CHAPTER 1 History of the Code Rules for Accreditation, Certification, and Related Issues
Richard Stevenson and Marcus Bressler	1-1
CHAPTER 2 The Maintenance Rule
C. Wesley Rowley	2-1
CHAPTER 3 Pipe Vibration Testing and Analysis
David E. Olson	3-1
CHAPTER 4 Stress Intensification Factors, Stress Indices, and Flexibility Factors
Anthony W. Paulin, Jr. and Everett C. Rodabaugh	4-1
CHAPTER 5 Code Design and Evaluation for Cyclic Loading–Sections III and VIII
William J. O’Donnell		5-1
CHAPTER 6 Perspective on Cyclic, Impact, and Impulse Loads
Michael A. Porter		6-1
CHAPTER 7 Operability and Functionality Qualification
Stephen R. Gosselin and Thomas C. Esselman		7-1
CHAPTER 8 Fluids
Frederick J. Moody		8-1
CHAPTER 9 Bolted-Flange Joints and Connections
William J. Koves	9-1
CHAPTER 10 The Evolution of U.S. Transportation Regulations for Radioactive Materials — An Updated Retrospective
Ronald S. Hafner		10-1
CHAPTER 11 Pipeline Integrity and Security
Allan Murray		11-1
CHAPTER 12 Decommissioning Technology Development
Harold E. Adkins and Anibal L. Taboas		12-1
CHAPTER 13 On-Site Storage, Transport, Consolidated Interim Storage, and Disposal of Used Nuclear Fuel
Krishna P. Singh	13-1
CHAPTER 14 Seismic Protection for Pressure Piping Systems
Chakrapani Basavaraju and Mohinder L. Nayyar	14-1
CHAPTER 15 Generation III + PWRs
E. Keith Schwab, Marty Parece and Masanori Onozuka	15-1
CHAPTER 16 New Generation of BWRs
Hardayal S. Mehta		16-1
CHAPTER 17 Future Code Needs for Very High Temperature Generation IV Reactors
William J. O’Donnell and Donald S. Griffin		17-1
CHAPTER 18 License Renewal and Aging Management
P.T. Kuo		18-1
CHAPTER 19 BWR Reactor Internals and Other BWR Issues
Hardayal S. Mehta		19-1
CHAPTER 20 PWR Reactor Vessel Integrity and Internals Aging Management
Hardayal Mehta, William L. Server and Timothy J. Griesbach	20-1
CHAPTER 21 PWR Reactor Vessel Alloy 600 Issues
Glenn A. White	21-1
CHAPTER 22 PRA and Risk-Informed Analysis
Ralph S. Hill III		22-1
CHAPTER 23 Standardization of Valves, Flanges, Fittings and Gaskets (ASME B16 Standard)
James Philip Ellenberger		23-1
CHAPTER 24
PART A: LESSONS LEARNED BASED ON SECTION VIII, DIVISION 1
James C. Sowinski		24-1
PART B: LESSONS LEARNED BASED ON SECTION VIII, DIVISION 2
David A. Osage		24-11
CHAPTER 25 Lessons Learned Based on Operating Experience, Section XI
Gary Park		25-1
CHAPTER 26
PART A: LESSONS LEARNED: INDUSTRY EXPERIENCE OF MATERIALS
John F. Grubb		26-1
PART B: LESSONS LEARNED: EXPERIENCE WITH NONMETALLIC MATERIALS IN STRUCTURAL/ PRESSURE BOUNDARY APPLICATIONS
C. Wesley Rowley	26-5
CHAPTER 27 ASME Section XI Developments in Evaluation Procedures for Nuclear Piping Degraded by Flaws and Corrosion Processes in Response to Lessons Learned
Douglas A. Scarth	27-1
CHAPTER 28 Lessons Learned in the Use of Pressure Relief Devices
Chip H. Eskridge and Joseph F. Ball		28-1
CHAPTER 29 Insights from Nuclear Utility Experience with PRA Applications	
Deepak Rao		29-1
PART B: NEW DELIBERATIONS IN NUCLEAR MODULAR CONSTRUCTION— WESTINGHOUSE SMALL
MODULAR REACTOR
Alexander W. Harkness	32-13
CHAPTER 30 Lessons Learned: NRC Experience
Chakrapani Basavaraju		30-1
CHAPTER 31 Power and Process Piping Lessons Learned
Jimmy E. Meyer		31-1
CHAPTER 32
PART A: A SCALABLE APPROACH TO COMMERCIAL NUCLEAR POWER: NUSCALE POWER’S NEW APPROACH TO SAFETY AND DEPLOYMENT OF NUCLEAR PLANTS
José N. Reyes and Daniel Ingersoll		32-1
CHAPTER 33 New Deliberations-Fusion Reactors
PART A: THEORETICAL BASES AND SCIENTIFIC FOUNDATIONS
James A. MahaffeyV		33-1
PART B: ITER
Brad Nelson		33-5
PART C: NUCLEAR FUSION
Irving Zatz		33-13
Index 	 I-1

PREFACE
This publication follows the phenomenal success of the three editions of the Companion Guide to the ASME Boiler & Pressure Vessel Codes and Standards published by ASME Press. ASME Boiler and Pressure Vessel Codes and Standards are arrived at by a consensus process from the deliberations of practicing engineers, professionals, academia, and regulators meeting several times a year.
The first edition of these books in two volumes was published in summer 2002, with the third edition of the “Companion Guide” published in summer 2009, which over time had been broken into three separate volumes. The first release of the latest editions of these books is the fourth edition of the Companion Guide to the ASME Boiler & Pressure Vessel and Piping Codes, which addressed Sections I through XII of the Boiler & Pressure Vessel Codes and B31 Codes and Standards in two volumes and was published in summer 2012. The other two, new “stand-alone” separate volumes, which include chapters of the third edition excluded from the fourth edition are: (a) Continuing and Changing Priorities of ASME B&PV Codes and Standards, and
(b) Global Applications of ASME B&PV Codes and Standards. This book addresses the Continuing and Changing Priorities of SME B&PV Codes and Standards and pursues the intent of the previous editions. This publication continues to focus on the criti- cal Public Safety issues discussed by experts in the first, and sub- sequent second and third editions. Being at the cross-roads of aging nuclear reactors seeking life extension with few on the threshold of new constructions, and even fewer considering per- manent shutdown, it is appropriate to chronicle the continuing and changing priorities. Given the changes in the demographics of the ASME Boiler and Pressure Vessel Code Members, it is appropriate to chronicle Continuing and Changing Priorities of ASME B&PV Codes and Standards since some Code Members are either seeking retirement or even fading away. It is appropriate to capture the 1634 combined years of the rich professional expertise of 43 contributors about the topics listed in the table of contents. In this Preface a chapter-wise sequential description is provided to highlight the contributors expertise for the chapters assigned to them.
Continuing the premise of the previous editions, this book has 699 pages of text, 527 equations, and 427 graphics including pictures, sketches and 94 tables and 1536 references and annotated bibliographical material. This publication has four parts as enumerated below, which shows the authoritative background of contributors chosen to chronicle the chapters assigned to them.
•	In Part 1, this book has updates by 16 Code experts and recognized professionals who addressed in 14 Chapters with  considerable revisions continue the thread of discussions of the third volume of the third edition, which were not included in the fourth edition of the “Companion Guide.” The revisions in this part deal with “Continuing Priorities of B&PV Codes and Standards” to recognize the changes in the cur- rent Code Editions and ongoing deliberations by the recognized professionals and Code Experts in the following chapters:
‘Code Rules for Accreditation, Certification’ replete with figures new and fresh insights are provided in the revisions by Richard Stevenson PE, a recognized Code Expert with nearly 4-decades of experience in National Board Conformity Assessment and leadership role in Code committee.
‘The Maintenance Rule’ is updated by Wesley C. Rowley PE, Code Committee Member who was at the helm of the ASME Board on Nuclear Codes and Standards for over twenty-five years.
’Pipe Vibration Testing and Analysis’ continues to be updated in 38 pages containing 35 graphics and 34 references by David E. Olson PE, current and long-standing Chairman of the ASME Operation and Maintenance Subgroup on Piping Systems.
‘Stress Intensification Factors, Stress Indices, and Flexibility Factors’ has been updated with 25 equations and 53 references is updated by a new contributor Anthony W. Paulin Jr., PE, versatile in the subject, President of an engineering test- ing and analysis the group he founded in 1991.
‘Code Design and Evaluation for Cyclic Loading – Sections III and VIII’ has been revised in 34 pages with 41 figures and 348 scholastic references by William O’Donnell, Ph.D., a reputed Code Committee member and a recognized expert in Failure Causation Analyses, who authored 96 papers in engineering mechanics, elastic-plastic fracture mechanics, strain limits and damage evaluation methods.
‘Perspective on Cyclic Impact, and Impulse Loads’ is revised with 52 references by Michael (Mike) A. Porter, a PV&PD expert in linear and non-linear stress analyses as well as computational structural dynamics.
‘Functionality and Operability Criteria’ continues to be authored by Stephen (Steve) R. Gosselin, a Sections III and XI Code Committee expert with 34 years commercial nuclear power industry experience focused primarily on fitness-for- service, structural integrity, safety, and reliability of pressure vessels and piping components; in addition this edition this chapter is co-authored by Thomas C. Esselman Ph.D., a senior executive of a reputed engineering consultancy with wide variety of engineering disciplines, including component and structure performance, aging, stress analysis, dynamics, seismic design and analysis, mechanical design, thermo- hydraulics, materials, materials degradation, and failure analysis.
‘Fluids’ was authored with 201 equations and 40 figures by Frederick J. Moody, an internationally renowned engineer with 41 years of consultancy experience with GE Nuclear Energy, and 28 years as adjunct professor adept in fluid mechanics, thermodynamics, heat transfer, and coupled fluid- structure interaction, pertaining to reactor and containment technology.
‘Bolted-Flange Joints and Connections’ is authored in 38 pages, 15 figures and 140 equations by William J. Koves Ph.D. PE, a code expert with 40 years of experience in the design, analysis and troubleshooting of equipment and air- craft, nuclear reactors, and petrochemical equipment structures. Author is holder of 27 US and 3 European patents.
‘The Evolution of U.S. Transportation Regulations for Radioactive Materials – A Retrospective’ is authored by Ronald F. Hafner, the continuing contributor in 24 pages and 33 references. Ronald Hafner has 50 years of experience in a variety of disciplines ranging from radar systems and nuclear instrumentation to non-destructive testing using gamma-ray sources and electronic devices, to nuclear reactor- and tritium facility operations, to regulatory issues associated with Department of Energy facilities and the transportation, stor- age, and disposal of radioactive materials.
‘Pipeline Integrity and Security’ initially co-authored in ‘Companion Guide’ is updated by Alan Murray Ph.D., PE, the retired Chief Engineer and Chief Safety Officer of a National Energy Board, Canada, an Adjunct Professor in the Mechanical Engineering Department, founding chair of the ASME Pipeline Systems Division in 2000, and coauthor of the very successful ASME books Pipeline Design and Construction: - A Practical Approach, and Pipeline Integrity Assurance. This chapter update is replete with 58 scholastic references, 26 equations and 47 figures and is provided with a wealth of authoritative information.
‘Decommissioning Technology Development’ updated in this book by a new contributor Harold E. Adkins of the US Fluid and Computational Engineering Group at Energy & Environment Directorate.
‘On-Site Storage, Transport, Consolidated Interim Storage, and Disposal of Used Nuclear Fuel’ is updated with fresh insights by the renowned Spent Fuel Specialist K. P. (Kris) Singh Ph.D., in this publication in 20 pages with 42 refer- ences, and 20 figures. Contributor is President and CEO of an International, diversified energy technology company that he founded in 1986. He is holder of an array of patents (over 50 U.S. and foreign patents granted, and some 15 in the process of being granted).
‘Seismic Protection for Pressure Piping Systems’ is a new chapter by a an internationally recognized specialist in the area of piping, valves, materials, and codes and standards who has 46 years of design engineering experience on more than 100 domestic and international mega fossil and nuclear power and other projects. He is the Editor-in-Chief of the much-acclaimed McGraw-Hill’s The Piping Handbook (1992). This chapter is co-authored by Chakrapani Basavaraju Ph.D., PE a proficient  engineer  with  USNRC, a member of Section III Code Committee,  with  insights  into seismic aspects of domestic and international plants.
 Contributors of this chapter provided 22 equations and 14 references.
•	In Part 2, this book has updates by 13 Code Experts and Recognized Professionals who addressed in 9 Chapters with considerable revisions which continue the thread of discussions of the third volume of the third edition which was not included in the fourth edition of ‘Companion Guide’. The revisions in this part deal with “Changing Priorities of B&PV Codes and Standards” which recognize the changes in the current Code Editions and ongoing deliberations as listed in the following:
‘The leading chapter of Part 2 of the book has three parts - AP1000® PWR in Part A addressed by Keith E. Schwab, a replacement contributor with 34 years of diverse experience with the design of utility power, petrochemical, and industrial facilities who brings wealth of new information for the cur- rent update; in ‘Part B: EPR’ is addressed by Chief Engineer and Vice- President of AREVA NP, Inc., responsible for oversight and control of pressurized water reactor and high temperature gas reactor designs planned for deployment in North America; and in ‘Part C: US-APWR’ is addressed by recognized and reputed replacement contributor Dr. Masanori Onozuka, vice president of Mitsubishi Nuclear Energy Systems, Inc., who has 30 years of experience in the research, design, analyses, and project management in nuclear related fields, including fusion research. Dr. Onozuka utilized his access to additional information in updating this part of the chapter.
‘New Generation of BWRs’ has been updated by Hardayal Mehta, Ph.D., PE, who has been with GE Nuclear Division (now, GE-Hitachi Nuclear Energy) since 1978, and currently holds the position of Chief Consulting Engineer. Dr. Mehta is a noted Code Expert, brings to the chapter his 40 years of experience in the areas of stress analysis, linear-elastic and elastic-plastic fracture mechanics, residual stress evaluation, and ASME Code related analyses pertaining to BWR components.
’Future Code Needs for Very High Temperature Generation IV Reactors’ has been updated with 31 equations by William O’Donnell Ph.D., and Donald Griffin Ph.D. Dr. O’Donnell, founder President of O’Donnell and Associates, an engineer- ing consulting firm specializing in design and analysis of structures and components evaluation of structural integrity, including corrosion fatigue, flaw sensitivity, crack propagation, creep rupture and brittle fracture is a versatile Code Expert.
‘License Renewal and Aging Management’ has been updated by Pao-Tsin Kuo Ph.D., PE, retired from US NRS where he was Director of License Renewal Division and is executive consultant to the regulatory bodies.
‘BWR Reactor Internals & Other BWR Issues’ has been updated by Dr. Mehta details about him are noted above. Dr. Mehta covers 28 pages, 21 equations, 34 figures and tables, and 132 references, unique ways in which the provisions of Section III and Section XI have been used in addressing the service-induced degradations in the BWR vessels, internals, and pressure boundary piping. Among the items covered are reactor internals, weld overlays, reactor vessel. He states that the most common form of service-induced cracking in the stainless steel and Ni-Cr-Fe components in the BWR pressure boundary is typically due to intergranular stress corrosion cracking (IGSCC).
’BWR Reactor Vessel Integrity & Internals Aging Management’ has been updated by Dr. Mehta, (as noted above) with the help of William Server who has more than thirty years of experience in materials applications, failure analyses, and structural integrity evaluations for the electric utility industry.
’PWR Reactor Vessel Alloy 600 Issues’ has been updated with 106 references and 26 graphics by Glenn White PE; he was the principal author of the Electric Power Research Institute (EPRI) safety assessment report for primary water stress corrosion cracking (PWSCC) of U.S. PWR Alloy 600 reactor vessel closure head penetrations.
‘PRA and Risk-Informed Analysis’; Ralph S. Hill III, PMP, is a Consulting Engineer with Westinghouse Electric Company in Pittsburgh, PA updated this chapter with 72 references. He has over 35 years of technical and management experience, including risk management, process evaluation, and project management consulting services to the U.S. Department of Energy in spent nuclear fuel, radioactive waste management, and nuclear materials disposition-related projects. Ralph is ASME Vice President Elect Nuclear Codes and Standards where he serves as Chairman of the Risk Management Task Group.
‘Standardization of Valves, Flanges Fittings, and Gaskets’ is a new chapter included in this book to address “Balance of Plant” issues. This has been contributed by James Phillip Ellenberger, a recognized Code Authority of B16 and B31 Committees. Mr. Ellenberger is an author of three technical Books – Boiler Code Simplified, Piping Code Simplified, Piping and Pipeline Calculations.
•	Part 3 is a new entity in response to the current needs of the nuclear industry. Considering that the industry had over four decades of learning curve and several of the experts engaged in the nuclear field are either retiring or even fading away it is appropriate to capture while the experts are still available to provide to the industry the “lessons learned”. In light of that opportunity 11 Experts, most of them associated with the development of the Code have been selected to address in 8 Chapters considered to be of dire importance. Thus, the following are new chapters that deal with “Changing Priorities of B&PV Codes and Standards” which recognize the changes in the current Code Editions and ongoing deliberations as listed in the following:
The first chapter deals with Section VIII which is the ‘mother Code’ of the Boiler and Pressure Vessel Codes in vogue to-day, an understanding of the pitfalls in the use if Section VIII can be immense use. As such the contributors selected for this purpose befit their reputation. In ‘Part A: Lessons Learned Based on Section VIII, Division 1 by James C. Sowinski’ and in ‘Part B: Lessons Learned Based on Section VIII, Division 2’ by David A. Osage’ appear as leading Chapter 24 of Part 3. James C. Sowinski PE is a Consulting Engineer for The Equity Engineering Group, Shaker Heights, Ohio. Sowinski was involved in the development of the new ASME, Section VIII, Division 2, Boiler and Pressure Vessel Code and was a contributing author of the ASME Section VIII, Division 2, Criteria and Commentary. David Osage, President and CEO of the Equity Engineering Group, Shaker Heights, Ohio, an internationally recognized industry expert for “Fitness-For-Service”. As the lead investigator and principal author of the new ASME, Section VIII, Division 2, Boiler and Pressure Vessel Code, he developed a new organization and writing style for this code. David was responsible for introducing the latest developments in materials, design, fabrication and inspection technologies.
‘Lessons Learned Based on Operating Experience, Section XI’ is by Gary Park. Park has worked in the Nuclear Industry since 1977. Park is currently the Chair of the Boiler and Pressure Vessel Standards Committee on Nuclear Inservice Inspection. His insights on the subject are valuable, him being on the Board on Nuclear Codes and Standards. He had been a member of the ASME Committees since 1996.
‘Lessons Learned: Industry Experience of Materials has been addressed in two Parts. Part A is titled: Lessons Learned - Industry Experience of Materials’ is by John F. Grubb Ph.D. PE. who has over 30 years’ experience with corrosion resistant alloys with primary areas of expertise being material environmental resistance, behavior and applications. He is co-inventor of several patented corrosion-resistant alloys. He has been active in Section II and Section VIII as Code Committee member and Chair of Sub-Groups.
Part B is Lessons Learned: Experience with Nonmetallic Materials in Structural/Pressure Boundary Applications, by C. Wesley Rowley PE. Rowley is a Vice President, Engineering & Technical Services, with The Wesley Corporation in Tucson, AZ. He is a recognized expert on non-metallic materials and non-metallic structural repairs and chaired several ASME committees and Task Groups on Nonmetallic Mate- rials and has been a member of the ASME Board on Nuclear Codes and Standards for over twenty-five years.
‘ASME Section XI Developments in Evaluation Procedures for Nuclear Piping Degraded by Flaws and Corrosion Processes in Response to Lessons Learned’ by Douglas A. Scarth Ph. D. provides authoritative insights into subject mat- ter. Scarth is currently a Technical Director – Fracture Programs with Kinectrics, Toronto, Canada and was previously with the Research Division of Ontario Hydro. His work experience associated with structural integrity evaluations of nuclear and fossil plant components containing flaws is very much reflected in his write-up. As Chair of the Section XI Working Group on Pipe Flaw Evaluation and actively involved with Section XI flaw and structural evaluations his write-up could be of immense value to the readers.
Pressure Relief Valves are extremely crucial in any pressure vessel or other pressure equipment such as boilers, piping, tankage and perhaps more so in nuclear applications which are however not discussed in the chapter titled ‘Lessons Learned in The Use of Pressure Relief Devices’ by Chip H. Eskridge PE and Joseph F. Ball PE. Chip Eskridge has over 30 years of experience in the petrochemical and power industries and is currently a Technology Manager for the Jacobs Engineering Group. Being a Chair of a B31.3 Process Piping Sub-Group and Member of ASME B31 Materials and API’s Pressure Relief Systems Committee the insights provided by him with the help of Joseph Ball regarding Pressure Relief Valves are of value to the readers. Joseph Ball has worked for The National Board of Boiler & Pressure Vessels Inspectors for 34 years and is currently the Director of the Pressure Relief Department for the organization.
‘Insights from Nuclear Utility Experience with PRA Applications’ by Deepak Rao PE has been with a noted utility, Entergy for over 30 years. He has been representing Entergy for several years at the EPRI Risk and Safety Management Advisory Group as well as the Nuclear Energy Institute’s industry Risk Applications Task Force. Thus, his perspective of lessons learned are considered valuable coming from the utility perspective, considering that Deepak Rao has been serving on the ASME/ANS Committee on PRA Standards for the past several years.
Another valuable perspective for lessons learned is from the regulators. Chakrapani Basvaraju Ph.D., PE contributed a chapter on ‘Lessons Learned: NRC Experience’ in which with 43 equations and 21 references, he dwells extensively on “Fukushima Lessons Learned”, and also provides valuable insights on Effect of LWR Environment on Fatigue Life of Nuclear Plant Components, Buried Pipe-Leakage Issues, HDPE for Replacement of Carbon Steel Piping In Safety Related Class 3 Buried Piping, BWR Steam Dryers for EPU Operation, RPV Indications In DOEL & TIHANGE NPP, Steam Generator Tube Leaks, and Issues for New Construction.
‘Power and Process Piping Lessons Learned’ by Jimmy E. Meyer PE with 62 valuable references provides a laudable write-up. We often get wrapped up with piping problems of Class 1, 2 and 3 but in fact process and power piping issues get equal attention of operators of nuclear, fossil or petro- chemical plants. Jimmy Meyer with over 35 years of experience in refining petrochemical, chemical, power generation and industrial facilities is perhaps one such person experienced in overall project coordination/management, pressure equipment, piping design, analysis, specifications, support design, mechanical system requirements and documentation requirements of power and process piping. This has been chronicled in this chapter.
Talking about the future is not easy, especially when we are stumbling through the current issues of nuclear power generation. Even ASME Code Committee members were less enthusiastic to spell out the “knitty gritty” details. However, invitation to the top- notch experts in the field worked out exceedingly well, and it is gratifying that in Part 4: Changing Priorities of BPV Codes and Standards: Future Discussions are captured in the following two chapters from the contributions of professional experts.
First chapter deals with New Deliberations in NUCLEAR – Modular Construction in two parts A and B. First, Part A: A Scalable Approach to Commercial Nuclear Power: Nuscale Power’s New Approach to Safety and Deployment of Nuclear Plants, is by José N. Reyes and Daniel Ingersoll. They discuss, a novel deployment approach - the factory-fabricated NuScale Power Module (NPM) that relies on well-known light-water reactor technology, significantly reducing techno- logical and regulatory risks. The principal author for this Part A is Jose N. Reyes Ph.D., Chief Technology Officer and co- founder of NuScale Power, LLC. He is also the co-designer of the NuScale passively cooled small nuclear reactor. He is an internationally recognized expert on passive safety system design, testing and operations for nuclear power plants. He has served as a United Nations International Atomic Energy Agency (IAEA) technical expert on passive safety systems. Co- author of this Part A is Daniel T. Ingersoll Ph.D. Daniel Ingersoll is Director of the Office of Research Collaborations for Nu-Scale Power. During his 34 years at Oak Ridge National Laboratory (ORNL) he was Senior Program Manager in the Small Modular Reactors R&D Office and National Technical Director for the U.S. Department of Energy’s Small Modular Reactor program at ORNL. He is the former chairman of the American Nuclear Society’s Radiation Protection and Shielding Division.
In Part B: New Deliberations in Nuclear Modular Construction - Westinghouse Small Modular Reactor is described by Alexander W. Harkness. Alexander W. Harkness is a Consulting Engineer and Design Lead for the Small Modular Reactor (SMR) development program with more than 23 years of nuclear industry experience covering areas of engineering, plant design, market- ing, component design and analysis.
The second chapter of Part 4 addresses New Deliberations - Fusion Reactors in three parts: Part A - Theoretical Bases and Scientific Foundations by James A. Mahaffey; Part B: ITER by Brad Nelson; and Part C: Nuclear Fusion by Irving Zatz.
In Part A: The fundamental principles of hydrogen fusion make this process seem inevitable as a method of commercial power production. It is a clean power process, producing no harmful byproduct, using an inexhaustible supply of fuel, and hydrogen fusion is the source of all energy release in the larger universe. The rationale of this argument has been expounded James A. Mahaffey Ph. D. with a 25-year career at the Georgia Tech Research Institute (GTRI) where he directed projects for the U.S. Defense Nuclear Agency, the U.S. National Ground Intelligence Center, the U.S. Air Force Air Logistics Center, Georgia Power Company, and other government and private industrial organizations, in such areas as nuclear power, non-linear analysis, digital systems design, and cold fusion.
In Part B: of this chapter written by Brad Nelson is a compila- tion of content from www.ITER.org and is attributable to the ITER team with additional information and figures attributable to the US ITER team, available at www.usiter.org. Brad Nelson is the chief engineer for the US ITER Project. His group provides engineering support to US ITER, and he interfaces with partner laboratories and the ITER International Organization. He has more than 35 years of experience in the design and analysis of experimental fusion energy research facilities and components. He has ten figures and 17 references and easily understandable textual content explaining the definition, description and role of ITER in making fusion reactors a reality!
In Part C: is probably an extension what is explained in Part A in explaining the fusion process that can be found on the Princeton University Plasma Physics Laboratory website (http://www.pppl.gov/about/fusion-basics). Part C has been con- tributed by Irving J. Zatz who is a Principal Engineer at the Princeton University Plasma Physics Laboratory (PPPL), which focuses on fusion energy research. In his 30 years of experience at PPPL and has Mr. Zatz has been extensively involved with the structural analysis and design of complex mechanical systems that have operating conditions in both high heat flux and cryo- genic environments. He has participated in numerous domestic and international fusion energy projects and collaborations, including ITER. He is on an ASME committee tasked with the development of a code case for fusion within the ASME Boiler and Pressure Vessel Standards.
The above expose provides an understanding of the experts who provide in their individual write-up “the continuing and changing priorities” that deserve attention of the readers. For a details of the contributor’s credentials readers are advised to refer to their “bios” and for a brief abstracts of the coverage in the individual chapter’s readers, should read the “introduction” part that appears in the ‘front matter’ of this book. Thus, in my opinion this book is different from all other “Companion Guide Volumes” I edited, especially the fourth edition of the Companion Guide to the ASME Boiler & Pressure Vessel and Piping Codes, which addressed Sections I through XII of the Boiler & Pressure Vessel Codes and B31 Codes and Standards published in summer 2012. This is true in case of the above Preface, which is a ‘gist’ of the priorities of the B&PV Codes covered in this publication that deserve reader’s attention.
K. R. Rao Ph.D., PE (Editor)