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
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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)
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 36071622
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRITTLENESS; CRACKS; DYNAMIC LOADS; FRACTURE PROPERTIES; PRESSURE VESSELS; PROBABILISTIC ESTIMATION; PROBABILITY; REACTOR COMPONENTS; STATIC LOADS; STRESS INTENSITY FACTORS; WWER TYPE REACTORS
- Descriptors DEC
- CALCULATION METHODS; CONTAINERS; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
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