Application of static and dynamic crack arrest theory to thermal shock experiment TSE-4
Description
A dynamic method of analysis developed by Battelle Columbus Laboratory (BCL) for a crack run--arrest event was applied to Oak Ridge National Laboratory (ORNL) thermal shock experiment TSE-4, which was conducted on an A508 steel cylinder [530 mm OD x 150 mm wall x 910 mm long (21 in. x 36 in.)] with a quench-only heat treatment. In this experiment, a long axial flaw with an initial depth of 11 mm propagated in a single jump to a depth of 23 mm and arrested. The dynamic analysis indicated that dynamic effects for the 12-mm extension were essentially negligible; thus the statically calculated arrest toughness (K/sub Ia/) was a good approximation of K/sub Im/. This K/sub Im/ (K/sub Ia/) value (127 MN m -3/2) was 24% less than K/sub Ic/ at the same temperature (1310C). The K/sub Im/ value deduced from the dynamic analysis of TSE-4 was 124 MN m-3/2, which is in good agreement with the statistically calculated value of K/sub Ia/ at arrest (127 MN m-3/2). Researchers at BCL obtained several values of K/sub ID/ for the TSE-4-type material. However, data were insufficient for determining a laboratory value of K/sub Im/, which could have been compared to the TSE-4 K/sub Im/ value. All values of K/sub ID/ obtained by BCL were greater than K/sub Ic/
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.
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Additional details
Publishing Information
- Imprint Pagination
- 33 p.
- Report number
- NUREG/CR--0767
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10486875
- Subject category
- S36: MATERIALS SCIENCE; S61: RADIATION PROTECTION AND DOSIMETRY; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CRACKS; ECCS; LOSS OF COOLANT; PIPELINES; QUENCHING; RUPTURES; SIZE; STEEL-ASTM-A508; TEMPERATURE DEPENDENCE; TESTING; THERMAL SHOCK
- Descriptors DEC
- ACCIDENTS; ALLOYS; CARBON ADDITIONS; FAILURES; HEAT TREATMENTS; IRON ALLOYS; IRON BASE ALLOYS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; STEELS; TRANSITION ELEMENT ALLOYS
Optional Information
- Secondary number(s)
- ORNL/NUREG--57.