Crack arrest behavior of reactor pressure vessel steels at high temperatures
Conference
·
OSTI ID:7242822
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
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CHARPY TEST
CONTAINERS
CRACK PROPAGATION
DATA
DESTRUCTIVE TESTING
EXPERIMENTAL DATA
FRACTURE MECHANICS
IMPACT TESTS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL TESTS
MECHANICS
NATIONAL ORGANIZATIONS
NUMERICAL DATA
ORNL
PRESSURE VESSELS
REACTOR MATERIALS
RESEARCH PROGRAMS
STEELS
TESTING
US AEC
US DOE
US ERDA
US NRC
US ORGANIZATIONS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CHARPY TEST
CONTAINERS
CRACK PROPAGATION
DATA
DESTRUCTIVE TESTING
EXPERIMENTAL DATA
FRACTURE MECHANICS
IMPACT TESTS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL TESTS
MECHANICS
NATIONAL ORGANIZATIONS
NUMERICAL DATA
ORNL
PRESSURE VESSELS
REACTOR MATERIALS
RESEARCH PROGRAMS
STEELS
TESTING
US AEC
US DOE
US ERDA
US NRC
US ORGANIZATIONS