Published 2000 | Version v1
Book

A study of crack growth in nuclear graphites using R-curve analysis

  • 1. Nuclear Materials Group, Dept. of Materials Science and Engineering, University fo Bath (United Kingdom)

Description

During service, moderator graphites are subject to neutron irradiation that induces dimensional changes and generates internal stresses. Historically, the fracture behaviour of poly-granular graphites has been characterized by linear-elastic fracture mechanics, but graphites exhibit marked non-linearity in stress-strain curves and irreversible deformation mechanisms like crack branching and bridging which are characteristic of elastic-plastic materials. The internal stresses generated eventually lead to cracking and ultimately failure of graphite components by fast fracture. In this paper, the crack growth resistance, R, is considered and is defined as the energy required per unit crack area increase and therefore includes both the elastic and plastic energy components of the fracture process. Two independent graphical methods to determine R have been evaluated. The first method requires the comparison of two adjacent load cycles (to zero load) to determine the envelope of energy consumed in propagating the crack whilst the second method compares the load displacement curve (without the need for load cycles) with that of an ideal linear elastic material. Both methods show similar results which differ from other carbon materials in that a relatively high resistance to crack initiation is observed followed by a slightly decreasing crack propagation and crack termination. (authors)

Part of:
Basic studies on high-temperature engineering

Additional details

Publishing Information

Publisher
Organisation for Economic Co-Operation and Development
Imprint Place
Paris (France)
Imprint Title
Basic studies on high-temperature engineering
Imprint Pagination
404 p.
Journal Page Range
p. 247-256

Conference

Title
1. information exchange meeting
Dates
27-29 Sep 1999
Place
Paris (France)

INIS

Country of Publication
France
Country of Input or Organization
Nuclear Energy Agency of the OECD (NEA)
INIS RN
31060265
Subject category
S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AGR TYPE REACTORS; CRACK PROPAGATION; DIAGRAMS; FRACTURE MECHANICS; GRAPHITE; MECHANICAL TESTS; STRAINS; STRESSES
Descriptors DEC
CARBON; ELEMENTS; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GCR TYPE REACTORS; GRAPHITE MODERATED REACTORS; INFORMATION; MATERIALS TESTING; MECHANICS; MINERALS; NONMETALS; REACTORS; TESTING

Optional Information