Abstract
Any fracture toughness specimen that can be made out of the broken halves of standard Charpy specimens may have exceptional utility for evaluation of reactor pressure vessels since it would allow one to determine and monitor directly actual fracture toughness instead of requiring indirect predictions using correlations established with impact data. The Charpy V-notch specimen is the most commonly used specimen geometry in surveillance programs and most likely to be used in advanced reactors as per ASME code. The advantage of the Mini-CT specimen technique is that multiple specimens can be machined from one half of a broken Charpy specimen, used in a standard surveillance capsule of a reactor pressure vessel. Up to now, most of the work on validation of this type of the specimens has been performed on base metal. In this study, Mini-CT specimens were used to perform fracture toughness characterization of low upper-shelf Linde 80 weld, designated WF-70. This weld was utilized in the Midland beltline weld and has been previously well characterized at ORNL with various types and sizes of fracture toughness specimens. The Mini-CT specimens were machined from broken previously tested Charpy V-notch specimens. Despite very small size and relatively small number of Mini-CT specimen tested, the transition fracture toughness temperature, To, derived from these Mini-CT specimens is in very good correspondence with T o reported from analysis of a large number of larger fracture toughness specimens.
Original language | English |
---|---|
Title of host publication | Codes and Standards |
Publisher | American Society of Mechanical Engineers (ASME) |
ISBN (Electronic) | 9780791857908 |
DOIs | |
State | Published - 2017 |
Event | ASME 2017 Pressure Vessels and Piping Conference, PVP 2017 - Waikoloa, United States Duration: Jul 16 2017 → Jul 20 2017 |
Publication series
Name | American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP |
---|---|
Volume | 1A-2017 |
ISSN (Print) | 0277-027X |
Conference
Conference | ASME 2017 Pressure Vessels and Piping Conference, PVP 2017 |
---|---|
Country/Territory | United States |
City | Waikoloa |
Period | 07/16/17 → 07/20/17 |
Bibliographical note
Publisher Copyright:© 2017 ASME.
Funding
1 Notice: This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC0500OR22725 with the US Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript or allow others to do so, for United States Government purposes. This research was sponsored by the U.S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability Program. The author wish to thank Dr. Keith Leonard for his support, Ron Swain for performing the tests, and Dr. Randy Nanstad for reviewing this paper.
Funders | Funder number |
---|---|
Office of Nuclear Energy, Light Water Reactor Sustainability Program | |
US Department of Energy | |
U.S. Department of Energy |