Assessment of dynamic fracture mechanics for the analysis of crack arrest in a pressurized thermal shock event. Final report. [Including crack arrest]
Technical Report
·
OSTI ID:5534027
The objective of this project was to assess the feasibility of a dynamic fracture mechanics approach for use in analyses of postulated pressurized thermal shock (PTS) events in nuclear pressure vessels. The work focused on a high strength steel (type 4340) and employed linear elastic fracture mechanics concepts exclusively. Four specific tasks were performed. These were to (1) conduct dynamic crack run/arrest experiments in different temperature and crack speed regimes, (2) perform generation-phase elastodynamic finite element analyses of the experiments to obtain dynamic fracture toughness properties, (3) extrapolate these results to develop an approximate representation of the dynamic fracture toughness of nuclear pressure vessel steel, and (4) use this property to compute run/arrest behavior under a typical PTS condition. It was found that the crack arrest toughness data obtained via a dynamic fracture mechanics approach was largely in agreement with the 4340 steel data obtained (in a much complex manner) by other investigators. More significantly, the feasibility of applying the procedures developed in this research for PTS analyses was conclusively demonstrated. These results also indicate that, while dynamic effects must be considered in obtaining crack arrest data from small-scale specimen testing, static analysis may suffice for evaluating crack arrest in a nuclear pressure vessel. Recommendations are given for the further research that is needed to enable practical use of the approach developed in this work. 18 refs., 20 figs., 2 tabs.
- Research Organization:
- Southwest Research Inst., San Antonio, TX (USA)
- OSTI ID:
- 5534027
- Report Number(s):
- EPRI-NP-4043; ON: TI85920654
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CONTAINERS
CRACK PROPAGATION
CRACKS
DATA
EXPERIMENTAL DATA
FRACTURE MECHANICS
FRACTURE PROPERTIES
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
MECHANICS
NUMERICAL DATA
PRESSURE VESSELS
REACTORS
RECOMMENDATIONS
STEELS
STRESS INTENSITY FACTORS
THERMAL SHOCK
VELOCITY
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CONTAINERS
CRACK PROPAGATION
CRACKS
DATA
EXPERIMENTAL DATA
FRACTURE MECHANICS
FRACTURE PROPERTIES
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
MECHANICS
NUMERICAL DATA
PRESSURE VESSELS
REACTORS
RECOMMENDATIONS
STEELS
STRESS INTENSITY FACTORS
THERMAL SHOCK
VELOCITY