Published 1995 | Version v1
Book

ASME limits and contradictions in the finite element analysis of pressure vessels

  • 1. Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

Description

This paper is not one more guideline but an independent contribution focusing stress classification and failure mechanism in a FE framework. The authors examined a typical support skirt and showed interesting relations between the collapse load obtained by finite element analysis and the loads allowed from the ASME stress limits. Different skirt geometry configurations - with different angles of attachments between cylinder and cone parts - and a pressure vessel head are investigated. These configurations permitted to observe the influence of larger bending stress in the collapse load. They also showed the bending stress relationship to the allowable loads when calculated using the ASME limits. Using elastic and limit load FE analyses, the present paper determines the collapse loads of the skirts and pressure vessel head. It is also established the relationships between the calculated collapse loads and limits dictated by the ASME Code Subsection NB. Based on the NB rules, it will be possible to observe how different methods of stress assessment, classification, and limits may influence in the design of pressure vessel parts. (author). 6 refs., 1 fig., 4 tabs

Part of:
Transactions of the 13. International Conference on Structural Mechanics in Reactor Technology. v. 2

Additional details

Publishing Information

Publisher
Editora de Universidade Federal do Rio Grande do Sul.
Imprint Place
Porto Alegre, RS (Brazil)
ISBN
85-7025-350-8
Imprint Title
Transactions of the 13. International Conference on Structural Mechanics in Reactor Technology. v. 2
Imprint Pagination
897 p.
Journal Page Range
p. 13-18.

Conference

Title
13. International Conference on Structural Mechanics in Reactor Technology.
Dates
13-18 Aug 1995.
Place
Porto Alegre, RS (Brazil).

Optional Information

Notes
Imprint:Conference organized by the International Association for Structural Mechanics in Reactor Technology and Universidade Federal do Rio Grande do Sul.