Fracture mechanical investigation of a thermo shock scenario for a VVER-440 RPV
Description
The paper describes the modelling and evaluation of a pressurized thermal shock (PTS) scenario in a VVER-440 reactor pressure vessel due to an emergency cooling. An axially oriented semi-elliptical crack is assumed to be located in the core welding seam. Two variants of fracture mechanical evaluation are performed: the analysis of a sub-cladding crack and of a surface crack. Three-dimensional finite element (FE) models are used to compute the global transient temperature and stress-strain fields. By using a three-dimensional submodel, which includes the crack, the local crack stress-strain field is obtained. Within the subsequent postprocessing using the J-integral technique the stress intensity factors KI along the crack front are obtained. The FE results are compared to analytical calculations proposed in the VERLIFE code. The stress intensity factors are compared to the fracture toughness curve of the weld material. (orig.)
Additional details
Additional titles
- Original title (English)
- 34. MPA Seminar 2008. Vortraege
Publishing Information
- Imprint Title
- 34. MPA seminar 2008. Proceedings
- Imprint Pagination
- 985 p.
- Journal Page Range
- 12 p.
- ISSN
- 1861-5414
- Report number
- INIS-DE--0519
Conference
- Title
- 34. MPA seminar 2008
- Original Conference Title
- 34. MPA Seminar 2008
- Dates
- 9-10 Oct 2008
- Place
- Stuttgart (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 40003920
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; CRACKS; DUCTILE-BRITTLE TRANSITIONS; FERRITIC STEELS; FINITE ELEMENT METHOD; FRACTURE MECHANICS; FRACTURE PROPERTIES; LOSS OF COOLANT; PRESSURE VESSELS; STRESS ANALYSIS; STRESS INTENSITY FACTORS; THERMAL SHOCK; V CODES; WELDED JOINTS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; ALLOYS; CALCULATION METHODS; CARBON ADDITIONS; COMPUTER CODES; CONTAINERS; DEPOSITION; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; MECHANICS; NUMERICAL SOLUTION; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; STEELS; SURFACE COATING; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Available as CD-ROM;34. MPA Seminar 2008. Vortraege