Abstract
The use of correlations is common in the research and development arena of the nuclear industry with the realization that some applications with direct implications to safety demand a more rigorous approach. Most correlations involve the relationship between two experimental properties, such as that between hardness and tensile strength. There are others that are much more complicated and are often designated models because they incorporate physically-based knowledge; examples of this are predictive correlations for irradiation-induced embrittlement of reactor pressure vessels (RPV). The objective of this paper is to collect and discuss many of the commonly used correlations for applications to nuclear RPVs. This paper identifies and discusses various correlations that relate easily measured properties to properties that are more difficult, more time consuming, or more expensive to measure. In the case of irradiated RPV materials, irradiation-induced changes in easily measured properties are related to the changes in those more difficult to measure. It is noted that recognition and understanding of the uncertainties associated with all correlations is highly important.
| Original language | English |
|---|---|
| Title of host publication | Materials and Fabrication |
| Publisher | American Society of Mechanical Engineers (ASME) |
| ISBN (Electronic) | 9780791851685 |
| 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 | 6B-2018 |
| ISSN (Print) | 0277-027X |
Conference
| Conference | ASME 2018 Pressure Vessels and Piping Conference, PVP 2018 |
|---|---|
| Country/Territory | Czech Republic |
| City | Prague |
| Period | 07/15/18 → 07/20/18 |
Funding
1 Notice of Copyright: This manuscript has been authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 with the U.S. 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, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan). The authors acknowledge the U.S. Department of Energy, Office of Nuclear Energy, the DOE-Sponsored Light Water Reactor Sustainability (LWRS) Program, and Dr. Keith Leonard, Manager of the LWRS Program Materials Pathway, for support.