Published 1995 | Version v1
Book

A two-parameter model to predict fracture in the transition

  • 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

Part of:
Transactions of the 13. International conference on structural mechanics in reactor technology. v. 4

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.