Probabilistic fracture mechanics application of dynamic crack arrest by static analogy
- 1. Tetra Engineering Group, Weatogue, CT (United States)
- 2. Electric Power Research Inst., Palo Alto, CA (United States)
- 3. ABB Combustion Engineering Nuclear Power, Windsor, CT (United States)
Description
This paper reports that the CE/EPRI Crack Arrest Algorithm is designed to predict the arrest behavior of rapidly extending cracks in reactor vessel steels. It is based on a series of tests performed by Combustion Engineering, Inc., where the dynamic behavior of flaws was investigated as these flaws extended into regions of tougher material. These tests demonstrated that the instantaneous stress intensity at the crack tip controlled arrest behavior. This stress intensity depends on the dynamic response of the vessel to the crack extension, and is significantly smaller than the stress intensity calculated for a static flaw of the same size. Thus arrest is much more likely than is predicted by conventional static methods. The new algorithm was incorporated into a computer program designed to perform probabilistic fracture mechanics analysis of PWR reactor vessels. The probabilistic analysis was used to compare the static and CE/EPRI (Static Analogy) crack arrest method for a wide range of transient events. The results show that where tougher material conditions (warmer metal) exist deeper in the wall, the Static Analogy method shows failure probabilities considerably lower than calculated using the static arrest models
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0808-4
- Imprint Title
- Pressure vessel integrity 1991
- Imprint Pagination
- 290 p.
- Journal Page Range
- p. 261-268.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23058100
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CALCULATION METHODS; CRACK PROPAGATION; DESIGN; DYNAMIC LOADS; FRACTURE MECHANICS; MATERIALS TESTING; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR VESSELS; SAFETY ANALYSIS; SIMULATION; STEELS
- Descriptors DEC
- ACCIDENTS; ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICS; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS