Published 1996 | Version v1
Book

Behavior of cracked cylinders under combined thermal and mechanical loading

  • 1. EDF/SEPTEN, Villeurbanne (France)
  • 2. CEA/DER/SERA/LDCS, St. Paul lez Durance (France)
  • 3. CEA/DMT/SEMT/RDMS, Gif-sur-Yvette (France)
  • 4. FRAMATOME/Tour FRA, Paris la Defense (France)

Description

Nuclear pressure vessels and pipings can be submitted in their life to severe mechanical and thermal loadings. Engineering methods easy to apply, but sufficiently accurate, are needed to assess the flaws. In the field of non-linear fracture mechanics a lot of work has been achieved for structures submitted to mechanical loadings. But for thermal loadings, and particularly for thermal gradients, only few contributions are available. The authors propose, here, to present the main results of a complete set of finite element computations, conducted in France by CEA, EDF and FRAMATOME, on cracked cylinders submitted to combined mechanical and thermal loads. The interaction between these two types of loads is analyzed in the cases of austenitic and ferritic structures. Moreover, these results are compared to the predictions obtained by simplified engineering methods (R6 procedure, JSA16, and JEDF approaches). Their domain of validity is also discussed

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-1770-9
Imprint Title
Fatigue and fracture -- 1996: Volume 1. PVP-Volume 323
Imprint Pagination
412 p.
Journal Page Range
p. 299-304.

Conference

Title
American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
Dates
21-26 Jul 1996.
Place
Montreal (Canada).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28018647
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
COMPARATIVE EVALUATIONS; FINITE ELEMENT METHOD; FRACTURE MECHANICS; NONLINEAR PROBLEMS; NUCLEAR POWER PLANTS; PIPES; PRESSURE VESSELS; THEORETICAL DATA; THERMAL STRESSES
Descriptors DEC
CALCULATION METHODS; CONTAINERS; DATA; EVALUATION; INFORMATION; MECHANICS; NUCLEAR FACILITIES; NUMERICAL DATA; NUMERICAL SOLUTION; POWER PLANTS; STRESSES; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-960706--.