The effect of cyclic and dynamic loads on carbon steel pipe
Creators
- 1. Battelle, Columbus, OH (United States)
Description
This report presents the results of four 152-mm (6-inch) diameter, unpressurized, circumferential through-wall-cracked, dynamic pipe experiments fabricated from STS410 carbon steel pipe manufactured in Japan. For three of these experiments, the through-wall crack was in the base metal. The displacement histories applied to these experiments were a quasi-static monotonic, dynamic monotonic, and dynamic, cyclic (R = -1) history. The through-wall crack for the third experiment was in a tungsten-inert-gas weld, fabricated in Japan, joining two lengths of STS410 pipe. The displacement history for this experiment was the same history applied to the dynamic, cyclic base metal experiment. The test temperature for each experiment was 300 C (572 F). The objective of these experiments was to compare a Japanese carbon steel pipe material with US pipe material, to ascertain whether this Japanese steel was as sensitive to dynamic and cyclic effects as US carbon steel pipe. In support of these pipe experiments, quasi-static and dynamic, tensile and fracture toughness tests were conducted. An analysis effort was performed that involved comparing experimental crack initiation and maximum moments with predictions based on available fracture prediction models, and calculating J-R curves for the pipe experiments using the η-factor method
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as TI96007099; NTIS; GPO.Files
27053094.pdf
Files
(2.3 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 90 p.
- Report number
- NUREG/CR--6438
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27053094
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CARBON STEELS; COMPARATIVE EVALUATIONS; CRACK PROPAGATION; DATA ANALYSIS; DYNAMIC LOADS; EXPERIMENTAL DATA; FRACTURE MECHANICS; FRACTURE PROPERTIES; MECHANICAL PROPERTIES; MECHANICAL TESTS; NUCLEAR POWER PLANTS; PIPES; STRAIN AGING; WELDED JOINTS
- Descriptors DEC
- AGING; ALLOYS; CARBON ADDITIONS; DATA; EVALUATION; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MATERIALS TESTING; MECHANICS; NUCLEAR FACILITIES; NUMERICAL DATA; POWER PLANTS; STEELS; TESTING; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS
Optional Information
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- BMI--2188.