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Continuing & changing priorities of the ASME boiler & pressure vessel codes and standards / editor K.R. Rao

By: Contributor(s): Resource type: Ressourcentyp: Buch (Online)Book (Online)Publisher number: 860199Language: English Publisher: New York, NY : American Society Of Mechanical Engineers, [2014]Description: 1 Online-Ressource (verschiedene Seitenzählungen, circa 800 Seiten) : IllustrationenISBN:
  • 9780791860199
Subject(s): Additional physical formats: 0791800288 | Print version: No title DDC classification:
  • 621.1/830218 23
LOC classification:
  • TJ289
DOI: DOI: 10.1115/1.860199Online resources: Summary: This comprehensive work written by ASME Codes & Standards experts was originally published as part of Volume 3 of the Companion Guide to the ASME Boiler & Pressure Vessel Code. This fully updated and expanded volume is now a stand-alone publication that addresses Continuing and Changing Priorities for the success of current and next generation Nuclear Reactors and Internals, License Renewal, Public Safety, and PRA Fuel issues. This book has four parts, the first dealing with continuing priorities of ASME Boiler and Pressure Vessel Codes and Standards and the remaining three parts dealing with changing priorities of the Code. The first part has 13 chapters written by 15 distinguished code authorities with updated information pertaining to continuing priorities. Distinctive in this part is the inclusion of new contributors who have added unique perspectives to the material that was first published in the third edition of the Companion Guide. Likewise the authors who previously updated the material in the third edition have contributed additional information. A new chapter on "seismic protection for pressure piping systems" reflects the importance of the topic especially in regard to aging nuclear reactors. Three distinctive parts of the book address changing priorities of ASME B&PV Codes and Standards. These are: "Changing Priorities;" "Lessons Learned;" and "Future Discussions."In Part 2, "Changing Priorities," there are nine chapters by 11 contributors who are not only Code experts but also recognized authorities in the topics covered by them. Part 3, "Perspectives of Lessons Learned," has eight chapters by 11 authoritative contributors who are also distinguished in the topics addressed by them. In light of the aging nuclear reactors in operation in the U.S. and around the world and the need for new reactors, it is appropriate to synthesize the expert experiences relating to selected topics. Part 4, "Future Discussions," is the culmination of the current thinking process for the use of nuclear energy for power generation. This part has two chapters written by five authors with recognized expertise in the subject matter. A unique feature of this publication is the inclusion of all author biographies and an introduction that synthesizes every chapter, along with an alphabetical listing of indexed termsSummary: History of the code rules for accreditation, certification, and related issues -- The maintenance rule -- Pipe vibration testing and analysis -- Stress intensification factors, stress indices, and flexibility factors -- Code design and evaluation for cyclic loading : sections III and VIII -- Perspective on cyclic, impact, and impulse loads -- Operability and functionality qualification -- Fluids -- Bolted-flange joints and connections -- The evolution of U.S. transportation regulations for radioactive materials : an updated retrospective -- Pipeline integrity and security -- Decommissioning technology development -- Omitted -- Seismic protection for pressure piping systems -- Generation III+ PWRs -- New generation of BWRs -- Future Code needs for very high temperature generation IV reactors -- License renewal and aging management -- BWR reactor internals and other BWR issues -- PWR reactor vessel integrity and internals aging management -- PWR reactor vessel alloy 600 issues -- PRA and risk-informed analysis -- Standardization of valves, flanges, fittings and gaskets (ASME B16 standard) -- Part A: lessons learned based on section VIII, division 1. Part B: lessons learned based on section VIII, division 2 -- Lessons learned based on operating experience, section XI -- Part A: lessons learned: industry experience of materials. Part B: lessons learned: experience with nonmetallic materials in structural/pressure boundary applications -- ASME section XI developments in evaluation procedures for nuclear piping degraded by flaws and corrosion processes in response to lessons learned -- Lessons learned in the use of pressure relief devices -- Insights from nuclear utility experience with PRA applications -- Lessons learned: NRC experience -- Power and process piping lessons learned -- Part A: a scalable approach to commercial nuclear power: nuscale power's new approach to safety and deployment of nuclear plants. Part B: new deliberations in nuclear modular construction, westinghouse small modular reactor -- new deliberations-fusion reactors. Part A: theoretical bases and scientific foundations. Part B: ITER. Part C: nuclear fusionPPN: PPN: 863168531Package identifier: Produktsigel: ZDB-240-ASM
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