Abstract
Mini-CT specimens are becoming a highly popular geometry for use in reactor pressure vessel (RPV) community for direct measurement of fracture toughness in the transition region using the Master Curve methodology. In the present study, Mini-CT specimens were machined from previously tested Charpy specimens of the Midland low upper-shelf Linde 80 weld in both, unirradiated and irradiated conditions. The irradiated specimens have been characterized as part of a joint ORNL-EPRI-CRIEPI collaborative program. The Linde 80 weld was selected because it has been extensively characterized in the irradiated condition by conventional specimens, and because of the need to validate application of Mini-CT specimens for low upper-shelf materials - a more likely case for some irradiated materials of older generation RPVs. It is shown that the fracture toughness reference temperatures, To, derived from these Mini-CT specimens are in good agreement with To values previously recorded for this material in the unirradiated and irradiated conditions. However, this study indicates that in real practice it is highly advisable to use a much larger number of specimens than the minimum number prescribed in ASTM E1921.
| Original language | English |
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| Title of host publication | Codes and Standards |
| Publisher | American Society of Mechanical Engineers (ASME) |
| ISBN (Electronic) | 9780791851586 |
| DOIs | |
| State | Published - 2018 |
| Event | ASME 2018 Pressure Vessels and Piping Conference, PVP 2018 - Prague, Czech Republic Duration: Jul 15 2018 → Jul 20 2018 |
Publication series
| Name | American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP |
|---|---|
| Volume | 1A-2018 |
| ISSN (Print) | 0277-027X |
Conference
| Conference | ASME 2018 Pressure Vessels and Piping Conference, PVP 2018 |
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| Country/Territory | Czech Republic |
| City | Prague |
| Period | 07/15/18 → 07/20/18 |
Funding
The author acknowledges the U.S. Department of Energy, Office of Nuclear Energy, and the Light Water Reactor Sustainability (LWRS) Program, and Dr. Keith Leonard, Manager of the Materials Pathway, for support. The author wishes to thank Drs. Xiang Chen and Randy Nanstad for reviewing this paper. 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.