Author: K. G. HogePublisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 132
Book Description
Evaluation of the Integrity of SEP Reactor Vessels
Author: K. G. HogePublisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 132
Book Description
Status of Usa Neuclear Reactor Pressure Vessel Surveillance for Radiation Effects
Author: Scientific and Technical Aerospace Reports
Author: Integrity of Reactor Pressure Vessels in Nuclear Power Plants
Author: Publisher:
ISBN: 9789201017093
Category : Business & Economics
Languages : en
Pages : 0
Book Description
This publication is intended to assist nuclear utilities in optimizing the service life of nuclear power plants. It reviews the latest research on the effects of neutron irradiation on the steels and welds of reactor pressure vessels within light water cooled and moderated reactors.
Status of USA Nuclear Reactor Pressure Vessel Surveillance for Radiation Effects
Author: Lendell E. SteelePublisher: ASTM International
ISBN: 9780803102293
Category : Technology & Engineering
Languages : en
Pages : 290
Book Description
Evaluation of the Integrity of Reactor Vessels Designed to ASME Code
Author: K. G. HogePublisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 80
Book Description
Companion Guide to the ASME Boiler & Pressure Vessel Code
Author: K. R. RaoPublisher: American Society of Mechanical Engineers
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 848
Book Description
This is Volume 1 of the fully revised second edition. Organized to provide the technical professional with ready access to practical solutions, this revised, three-volume, 2,100-page second edition brings to life essential ASME Codes with authoritative commentary, examples, explanatory text, tables, graphics, references, and annotated bibliographic notes. This new edition has been fully updated to the current 2004 Code, except where specifically noted in the text. Gaining insights from the 78 contributors with professional expertise in the full range of pressure vessel and piping technologies, you find answers to your questions concerning the twelve sections of the ASME Boiler and Pressure Vessel Code, as well as the B31.1 and B31.3 Piping Codes. In addition, you find useful examinations of special topics including rules for accreditation and certification; perspective on cyclic, impact, and dynamic loads; functionality and operability criteria; fluids; pipe vibration; stress intensification factors, stress indices, and flexibility factors; code design and evaluation for cyclic loading; and bolted-flange joints and connections.
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development AdministrationPublisher:
ISBN:
Category : Medicine
Languages : en
Pages : 852
Book Description
Nuclear Science Abstracts
Author: Fatigue Assessment in Light Water Reactors for Long Term Operation
Author: IAEAPublisher: International Atomic Energy Agency
ISBN: 9201284225
Category : Technology & Engineering
Languages : en
Pages : 168
Book Description
Fatigue is a major element in time limited ageing analysis for long term operation of nuclear power plants (NPPs). It is important to understand how cracks occur and grow as a result of fatigue, and then assess fatigue failure. In the design and operating phase of NPPs, it is essential to consider the concurrent loadings associated with the design transients, thermal stratification, seismically induced stress cycles, and all relevant loads due to the various operational modes. After repeated cyclic loading, crack initiation can occur at the most highly affected locations if sufficient localized micro-structural damage has accumulated. This publication provides practical guidelines on how to identify and manage fatigue issues in NPPs. It explains the mechanism of fatigue, identifies which elements are the major contributors, and details how fatigue can be minimized in the design phase for new NPPs.