Crack arrest behavior of reactor pressure vessel steels at high temperatures

Conference · Fri Jan 01 00:00:00 EST 1988

OSTI ID:7242822

Pugh, C E; Naus, D J; Bass, B R

The Heavy-Section Steel Technology Program at the Oak Ridge National Laboratory under the sponsorship of the US Nuclear Regulatory Commission is conducting experimental and analytical studies to improve the understanding of conditions that govern the initiation, rapid propagation, arrest and ductile tearing of cracks in reactor pressure vessel (RPV) steels. In support of this objective, large-scale wide-plate experiments are performed to generate crack-arrest toughness data for RPV steels at temperatures approaching and above the onset of Charpy upper-shelf behavior. Analytical studies are addressing the role of dynamics and nonlinear rate-dependent (i.e., viscoplastic) effects in the interpretation of crack run-arrest events in these ductile materials. A summary of the wide-plate tests performed to date is presented, including details of test procedures, test data, and results of analyses performed to date. The importance of incorporating viscoplastic effects into dynamic analysis of crack run-arrest events in these strain-rate sensitive steels is examined through applications of selected proposed viscoplastic constitutive equations and fracture parameters to the interpretation of data from the wide-plate tests. The crack-arrest data are compared with those from small ASTM-type specimens and other large structural tests.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 7242822
• Report Number(s): CONF-8805141-2; ON: DE88011833; TRN: 88-023167
• Resource Relation: Conference: IAEA specialists' meeting on fracture mechanics verification by large-scale testing, Stuttgart, F.R. Germany, 25 May 1988; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
REACTOR MATERIALS
CRACK PROPAGATION
RESEARCH PROGRAMS
CHARPY TEST
EXPERIMENTAL DATA
FRACTURE MECHANICS
ORNL
PRESSURE VESSELS
STEELS
US NRC
ALLOYS
CONTAINERS
DATA
DESTRUCTIVE TESTING
IMPACT TESTS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL TESTS
MECHANICS
NATIONAL ORGANIZATIONS
NUMERICAL DATA
TESTING
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220200* - Nuclear Reactor Technology- Components & Accessories
360103 - Metals & Alloys- Mechanical Properties