Pressure vessel integrity 1991

Conference · Mon Dec 31 23:00:00 EST 1990

OSTI ID:5534339

Bhandari, S ^[1]; Doney, R O; McDonald, M S ^[2]; Jones, D P; Wilson, W K ^[3]; Pennell, W E ^[4]

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1. Framatome (FR)
2. ABB Combustion Engineering Nuclear Power (US)
3. Westinghouse Bettis Atomic Power Laboratory (US)
4. Oak Ridge National Laboratory (US)

This volume contains papers relating to the structural integrity assessment of pressure vessels and piping, with special emphasis on nuclear industry applications. The papers were prepared for technical sessions developed under the sponsorship of the ASME Pressure Vessels and Piping Division Committees for Codes and Standards, Computer Technology, Design and Analysis, and Materials Fabrication. They were presented at the 1991 Pressure Vessels and Piping Division Conference in San Diego, California, June 23-27. The primary objective of the sponsoring organization is to provide a forum for the dissemination and discussion of information on development and application of technology for the structural integrity assessment of pressure vessels and piping. This publication includes contributions from authors from Australia, France, Japan, Sweden, Switzerland, the United Kingdom, and the United States. The papers here are organized in six sections, each with a particular emphasis as indicated in the following section titles: Fracture Technology Status and Application Experience; Crack Initiation, Propagation and Arrest; Ductile Tearing; Constraint, Stress State, and Local-Brittle-Zones Effects; Computational Techniques for Fracture and Corrosion Fatigue; and Codes and Standards for Fatigue, Fracture and Erosion/Corrosion.

• OSTI ID: 5534339
• Report Number(s): CONF-910602--; ISBN: 0-7918-0808-4
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220504 -- Nuclear Reactor Technology-- Environmental Aspects-- Design Basis & Hypothetical Accidents-- (1992-)
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ABSTRACTS
ALLOYS
CONTAINERS
DESIGN
DOCUMENT TYPES
ENGINEERING
FATIGUE
FRACTURE MECHANICS
IRON ALLOYS
IRON BASE ALLOYS
LEADING ABSTRACT
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICS
MEETINGS
PHYSICAL RADIATION EFFECTS
PROBABILISTIC ESTIMATION
RADIATION EFFECTS
REACTOR SAFETY EXPERIMENTS
REACTOR VESSELS
RESIDUAL STRESSES
SAFETY ANALYSIS
SAFETY ENGINEERING
SAFETY STANDARDS
SERVICE LIFE
SPECIFICATIONS
STANDARDS
STEELS
STRESSES
TESTING
THERMAL SHOCK