Published 1995 | Version v1
Book

PVRC sponsored tasks on elastic analysis of nozzle corner cracks

  • 1. Westinghouse Electric Corporation, Madison, PA (United States). Nuclear Services Division
  • 2. Electricite de France, Lyon (France)
  • 3. Framatome, Paris-La Defense (France). Nuclear Operations

Description

Over the past decade, PVRC sponsored a number of projects on the analysis of nozzle corner cracks in pipes and vessels. These projects included elastic and elastic plastic analyses. The current paper is to discuss and report on four PVRC projects involving elastic analysis of nozzle corner cracks. A critical evaluation for corner cracks in radial nozzles was performed following a thorough review of all available analysis techniques and experimental results for pipes/vessels subjected to internal pressures. Recommendations for a simplified approach and future research were provided. Need of additional analysis/data for very shallow cracks was also identified. Analytical work using boundary integral equation method was performed for a radial nozzle subjected to internal pressure. The results generally agreed with the earlier assessments. Analysis of an oblique nozzle subjected to internal pressure was performed for a number of crack sizes in the acute crotch area of the nozzle corner by an influence coefficient type approach. Additional work was done to collect experimental data to validate the analytical results for nozzle corner cracks

Additional details

Additional titles

Augmented title (English)
Pressure Vessel Research Council

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-1335-5
Imprint Title
Fatigue and fracture mechanics in pressure vessels and piping. PVP-Volume 304
Imprint Pagination
594 p.
Journal Page Range
p. 35-44.

Conference

Title
Joint ASME/JSME pressure vessels and piping conference.
Dates
23-27 Jul 1995.
Place
Honolulu, HI (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27026102
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
CALCULATION METHODS; CRACKS; EVALUATION; FRACTURE MECHANICS; NOZZLES; NUCLEAR POWER PLANTS; PRESSURE VESSELS; RESEARCH PROGRAMS; STRESS INTENSITY FACTORS; THEORETICAL DATA
Descriptors DEC
CONTAINERS; DATA; INFORMATION; MECHANICS; NUCLEAR FACILITIES; NUMERICAL DATA; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-950740--.