Assessment of cracked pipes in primary piping systems of PWR nuclear reactors
Description
Pipes related to the Primary System of Pressurized Water Reactors (PWR) are manufactured from high toughness austenitic and low alloy ferritic steels, which are resistant to the unstable growth of defects. A crack in a piping system should cause a leakage in a considerable rate allowing its identification, before its growth could cause a catastrophic rupture of the piping. This is the LBB (Leak Before Break) concept. An essential step in applying the LBB concept consists in the analysis of the stability of a postulated through wall crack in a specific piping system. The methods for the assessment of flawed components fabricated from ductile materials require the use of Elasto-Plastic Fracture Mechanics (EPFM). Considering that the use of numerical methods to apply the concepts of EPFM may be expensive and time consuming, the existence of the so called simplified methods for the assessment of flaws in piping are still considered of great relevance. In this work, some of the simplified methods, normalized procedures and criteria for the assessment of the ductile behavior of flawed components available in literature are described and evaluated. Aspects related to the selection of the material properties necessary for the application of these methods are also discussed. In a next .step, the methods are applied to determine the instability load in some piping configurations under bending and containing circumferential through wall cracks. Geometry and material variations are considered. The instability loads, obtained for these piping as the result of the application of the selected methods, are analyzed and compared among them and with some experimental results obtained from literature. The predictions done with the methods demonstrated that they provide consistent results, with good level of accuracy with regard to the determination of maximum loads. These methods are also applied to a specific Study Case. The obtained results are then analyzed in order to give support to the preliminary verification of the applicability of the LBB concept to this Case. Finally, some conclusions and recommendations are presented. (author)
Availability note (English)
Available from INIS in electronic formFiles
40103840.pdf
Files
(11.8 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:940cf578592bd4491d6495c63535f0a7
|
11.8 MB | Preview Download |
Additional details
Additional titles
- Original title (Portuguese)
- Avaliacao de tubulacoes trincadas em sistemas primarios de reatores nucleares PWR
Publishing Information
- Imprint Pagination
- 182 p.
- Report number
- INIS-BR--6203
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 40103840
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- CRACK PROPAGATION; CRACKS; DEFECTS; DUCTS; FRACTURE MECHANICS; FRACTURE PROPERTIES; FRACTURES; HEAT PIPES; PIPES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; THERMAL FRACTURES
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; FRACTURES; MECHANICAL PROPERTIES; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 81 refs., 31 figs., 34 tabs.