A two-parameter model to predict fracture in the transition
Creators
- 1. Tennessee Univ., Knoxville, TN (United States)
- 2. Oak Ridge National Lab., TN (United States)
Description
A model is proposed that uses a numerical characterization of the crack tip stress field modified by the J - Q constraint theory and a weak link assumption to predict fracture behavior in the transition for reactor vessel steels. This model predicts the toughness scatter band for a component model from a toughness scatter band measured on a test specimen geometry. The model has been applied previously to two-dimensional through cracks. Many applications to actual components structures involve three-dimensional surface flaws. These cases require a more difficult level of analysis and need additional information. In this paper, both the current model for two-dimensional cracks and an approach needed to extend the model for the prediction of transition fracture behavior in three-dimensional surface flaws are discussed. Examples are presented to show how the model can be applied and in some cases to compare with other test results. (author). 13 refs., 7 figs
Additional details
Publishing Information
- Publisher
- Editora da Universidade Federal do Rio Grande do Sul.
- Imprint Place
- Porto Alegre, RS (Brazil)
- ISBN
- 85-7025-351-6
- Imprint Title
- Transactions of the 13. International conference on structural mechanics in reactor technology. v. 4
- Imprint Pagination
- 860 p.
- Journal Page Range
- p. 833-842.
Conference
- Title
- 13. International conference on structural mechanics in reactor technology.
- Dates
- 13-18 Aug 1995.
- Place
- Porto Alegre, RS (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 28061694
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; FRACTURE MECHANICS; FRACTURES; NUCLEAR ENGINEERING; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR TECHNOLOGY; REACTOR VESSELS; REACTORS; RELIABILITY; RISK ASSESSMENT; SAFETY ANALYSIS; SYSTEMS ANALYSIS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ENGINEERING; FAILURES; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; THERMAL POWER PLANTS
Optional Information
- Notes
- Imprint:Conference organized by the International Association for Structural Mechanis in Reactor Technology and Universidade Federal do Rio Grande do Sul.