Test report on experimental stress analysis of a 24 inch diameter tee (ORNL T-12)
Description
The experimental stress analysis and low cycle fatigue test of one 24'' x 24'' x 10'' schedule 40 carbon steel, ANSI B16.9 tee performed by Combustion Engineering, Inc. is described. The tee was instrumented with 230 rectangular strain gage rosettes. Elastic data was obtained for 12 loading conditions consisting of internal pressure and orthogonal pure moments and orthogonal direct forces applied individually to the free branch and run ends of the tee. One of the run ends of the tee was ''built in'' throughout the test. All loads were applied through pipe extensions welded to the tee. The tee was tested to failure in a low cycle pressure fatigue test with a cyclic internal pressure between 0 psi and 1800 psi. A through-the-wall fatigue crack occurred at 76620 cycles. Significant test results are summarized and compared with design values tabulated in the ASME Boiler and Pressure Vessel Code, Section III, 1971. (U.S.)
Availability note (English)
MF available from INIS under the Report Number.Files
6213626.pdf
Files
(7.4 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:05c5a86596595c420368144b1c3cbf18
|
7.4 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 233 p.
- Report number
- ORNL-SUB--3310-4
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 6213626
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CARBON STEELS; CRACKS; FATIGUE; PIPE FITTINGS; PIPE JOINTS; PWR TYPE REACTORS; STRAINS; STRESS ANALYSIS; TESTING
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MECHANICAL PROPERTIES; REACTORS; STEELS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- For Oak Ridge National Lab., TN.
- Secondary number(s)
- CENC--1237.