Published 1987
| Version v1
Book
Failure behaviour of a piping system with a circumferentially orientated flaw - analytical and experimental investigations
- 1. Valtion Teknillinen Tutkimuskeskus, Helsinki (Finland)
- 2. Stuttgart Univ. (Germany, F.R.). Staatliche Materialpruefungsanstalt
- 3. Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projektbereich Heissdampfreaktor - Sicherheitsprogramm/Handhabungstechnik
Description
The rate of fatigue crack growth was slower in the test as had been expected from ASME XI wet-curve and a preliminary results of an autoclave fatigue test. LBB conditions were achieved in the test as could be predicted from calculated MFE-results. The analytical LBB prediction methods showed that the loading capacity of the weakened cross section was not reached and thus a leak type failure was expected. (orig./HP)
Additional details
Publishing Information
- Publisher
- Balkema.
- Imprint Place
- Rotterdam (Netherlands)
- ISBN
- 90-6191-768-9
- Imprint Title
- Transactions of the 9th international conference on structural mechanics in reactor technology. Vol. G
- Imprint Pagination
- 575 p.
- Journal Page Range
- p. 409-414.
Conference
- Title
- 9. biennial international conference on structural mechanics in reactor technology (SMIRT-9).
- Dates
- 17-21 Aug 1987.
- Place
- Lausanne (Switzerland).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 19068723
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; DEFECTS; DYNAMIC LOADS; FAILURES; FEEDWATER; FERRITIC STEELS; FRACTURE MECHANICS; LEAKS; LOW ALLOY STEELS; NUMERICAL SOLUTION; PIPES; REACTOR SAFETY EXPERIMENTS; STEAM LINES
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICS; OXYGEN COMPOUNDS; PIPELINES; POLAR SOLVENTS; POWER REACTORS; REACTORS; SOLVENTS; STEELS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS