Crack behaviour of pipes under internal pressure and simultaneous external bending moment
- 1. Stuttgart Univ. (Germany, F.R.). Staatliche Materialpruefungsanstalt
Description
To investigate the strength behaviour, the influence of toughness to crack initiation and instability, the strain behaviour, the crack opening as well as the leak-before-break behaviour of artificially cracked piping, pipe bend tests were carried out. The dimensions of the pipes were 800 mm O.D. and 47 mm wall thickness, similar to the dimensions of the main cooling piping system of a 1300 MWe German PWR plant. Two types of nuclear grade materials similar to A 533 Cl 2 were used with high upper shelf impact energy of 50 and 150 J. The pipes were weakened by circumferential oriented surface notches respectively by through-wall flaws having a length of 60 degrees and various depths. The 5 m-long pipe, closed on both ends, was mounted into a newly developed 10 MNm 4-point bending device for loading. After heating up to 3000C and pressurizing up to 15 MPa, the bending moment was increased until failure occurred. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 112
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 173-182
- ISSN
- 0029-5493
- CODEN
- NEDEA
Conference
- Title
- The contribution of component and large specimen testing to structural integrity assessment methodology.
- Original Conference Title
- 13. MPA Seminar ueber Sicherheit und Verfuegbarkeit in der Anlagentechnik: Der Beitrag der Komponenten- und Grossprobenpruefung zur Beurteilung von Bauteilen und Anlagen
- Acronym
- 13. MPA seminar on safety and reliability of pressure components
- Dates
- 8-9 Oct 1987.
- Place
- Stuttgart (Germany, F.R.).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 20061148
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENDING; BWR TYPE REACTORS; CRACKS; DEFECTS; DYNAMIC LOADS; FLUID-STRUCTURE INTERACTIONS; FRACTURE MECHANICS; FRACTURE PROPERTIES; LOSS OF COOLANT; PIPE FITTINGS; PIPES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; RESEARCH PROGRAMS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; DEFORMATION; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS