Published 2003 | Version v1
Miscellaneous Open

New approaches for evaluation of brittle strength of reactor pressure vessels

  • 1. 'Prometej' Central Research Institute of Structural Materials, St. Petersburg (Russian Federation)
  • 2. Research and Development Institute of Power Engineering, Moscow (Russian Federation)

Description

Based on the Master curve conception, condition of brittle strength is formulated for heterogeneous distribution of stress intensity factor along crack front and non-monotonic, non-isothermic loading. This formulation includes the elaborated procedure for taking into account the effects of shallow cracks and biaxial loading on fracture toughness. It is concluded as follows: (1) A condition of brittle strength is formulated for reactor pressure vessel with crack-like flaw in probabilistic statement. As the condition of brittle strength it is taken condition Pf < Pf(bar) where Pf is fracture probability, and Pf(bar) is a given level of fracture probability. Formulation of this condition is based on the weakest link model and takes into account a variation of the stress intensity factor KI and KIC along the crack front. (2) Dependencies are proposed which allow to take into account the shallow crack effect and the biaxial loading effect on fracture toughness of reactor pressure vessel steels. (3) Using approaches presented in the present paper allows one to decrease conservatism and to increase adequacy of evaluations of brittle strength of reactor pressure vessels. Now these approaches have been included in Russian Standard on evaluation of brittle fracture of RPV of WWER type

Files

36071622.pdf

Files (271.0 kB)

Name Size Download all
md5:2f82a2f3cc4a99b0af9513f750e54536
271.0 kB Preview Download
Part of:
Proceedings of the 17th international conference on structural mechanics in reactor technology

Additional details

Publishing Information

Publisher
Vysoka skola technicka
Imprint Place
Brno (Czech Republic)
Imprint Title
Proceedings of the 17th international conference on structural mechanics in reactor technology
Imprint Pagination
[3216 p.]
Journal Page Range
p. 1034-1041
Report number
INIS-CZ--0039

Conference

Title
17. international conference on structural mechanics in reactor technology
Acronym
SMIRT 17
Dates
17-22 Aug 2003
Place
Prague (Czech Republic)

Optional Information

Notes
Presented within section G01: Fracture mechanics - Reactor pressure vessel integrity I. 5 figs., 17 refs. Imprint:Published on CD-ROM in the PDF format for Adobe Acrobat; contact: Prof. S. Vejvoda, Institute of Applied Mechanics, Brno University of Technology, Brno, Czech Republic