Crack propagation in high strain regions of a steel containment
Description
During a severe accident, a containment may develop a controlled relatively small leak before the pressure reaches the point where general rupture of the shell occurs. Another hypothesis states that an overall failure will occur with total release of the vessel contents. This work represents a preliminary study to predict crack propagation from an initially small defect in a high strain location in a typical steel containment. The J integral approach is used. A virtual crack extension method for calculating J is developed for use with general finite element programs. Two through cracks with different lengths were found to be unstable at the pressure which caused a surface crack to propagate through the containment thickness. In other words, the resulting through crack will not be stable and general failure will occur with the almost instantaneous release of the vessel contents
Additional details
Publishing Information
- Imprint Title
- Proceedings of the third workshop on containment integrity
- Journal Page Range
- p. 479-494.
- Report number
- NUREG/CP--0076
Conference
- Title
- 3. workshop on integrity of containments for nuclear power plants.
- Dates
- 21-23 May 1986.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18086123
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SYSTEMS; CRACK PROPAGATION; CRACKS; DEFECTS; ELASTICITY; FAILURES; FINITE ELEMENT METHOD; LEAKS; MECHANICAL PROPERTIES; NUCLEAR POWER PLANTS; PLASTICITY; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR SAFETY; RISK ASSESSMENT; STEELS; STRAINS
- Descriptors DEC
- ACCIDENTS; ALLOYS; CARBON ADDITIONS; CONTAINMENT; IRON ALLOYS; IRON BASE ALLOYS; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; SAFETY; THERMAL POWER PLANTS