Analysis of ASME Boiler, Pressure Vessel, and Nuclear Components in the Creep Range
Second Edition
The latest edition of the leading resource on elevated temperature design
In the newly revised Second Edition of Analysis of ASME Boiler, Pressure Vessel, and Nuclear Components in the Creep Range, a team of distinguished engineers delivers an authoritative introduction to the principles of design at elevated temperatures. The authors draw on over 50 years of experience, explaining the methodology for accomplishing a safe and economical design for boiler and pressure vessel components operating at high temperatures. The text includes extensive references, offering the reader the opportunity to further their understanding of the subject.
In this latest edition, each chapter has been updated and two brand-new chapters added–the first is Creep Analysis Using the Remaining Life Method, and the second is Requirements for Nuclear Components. Numerous examples are included to illustrate the practical application of the presented design and analysis methods. It also offers:
* A thorough introduction to creep-fatigue analysis of pressure vessel components using the concept of load-controlled and strain-deformation controlled limits
* An introduction to the creep requirements in API 579/ASME FFS-1 ‘Remaining Life Method’
* A summary of creep-fatigue analysis requirements in nuclear components
* Detailed procedure for designing cylindrical and spherical components of boilers and pressure vessels due to axial and external pressure in the creep regime
* A section on using finite element analysis to approximate fatigue in structural members in tension and bending
Perfect for mechanical engineers and researchers working in mechanical engineering, Analysis of ASME Boiler, Pressure Vessel, and Nuclear Components in the Creep Range will also earn a place in the libraries of graduate students studying mechanical engineering, technical staff in industry, and industry analysts and researchers.
A propos de l’auteur
Maan H. Jawad, Ph D, is President of Global Engineering and Technology in the United States, a firm that offers engineering consulting to the pressure vessel, power, petrochemical, and nuclear industries. Previously, he served as Director of Engineering at the Nooter Corporation that fabricates pressure vessels for the boiler, petrochemical, and nuclear industries.
Robert I. Jetter has over 50 years of experience in the design and structural evaluation of nuclear components and systems for elevated temperature service. He participated in and directed design of early sodium cooled reactors and space power plants through all the US LMFBR programs. He currently consults on the development and application of elevated temperature design criteria for advanced nuclear applications.
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