ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
Education and training to support Canadian nuclear workforce development
Along with several other nations, Canada has committed to net-zero emissions by 2050. Part of this plan is tripling nuclear generating capacity. As of 2025, the country has four operating nuclear generating stations with a total of 17 reactors, 16 of which are in the province of Ontario. The Independent Electricity System Operator has recommended that an additional 17,800 MWe of nuclear power be added to Ontario’s grid.
Jian Cheng, Kewei Fang, Kexun Fei, Qiang Wang, Bo Li, Eduardo B. Farfán
Nuclear Technology | Volume 211 | Number 3 | March 2025 | Pages 584-597
Research Article | doi.org/10.1080/00295450.2024.2344912
Articles are hosted by Taylor and Francis Online.
Corrosion-resistant iron with nickel and chromium (CRDINiCr) is often used in butterfly valves for flow control at nuclear power plants, where resistance to corrosion, oxidation, and wear is significant. In this study, a failure analysis of a CRDINiCr alloy butterfly valve was performed by combining morphology characterization and in situ elemental composition analysis of failure of various regions of the valve. Based on the testing and analysis conducted in this study, it was determined that the inspected valve body material exhibited several defects, including poor graphitization, porosity, and the presence of eutectic carbides. These imperfections compromised the required plasticity criteria, resulting in significant embrittlement of the material. Therefore, under the impact stresses applied during the pressure testing, these vulnerabilities facilitated rapid crack initiation and propagation. The presence of such defects significantly compromised the material’s resistance to fracture under dynamic loading conditions, underscoring the critical importance of stringent quality control in the production of such materials to ensure their reliability and performance in operational settings at nuclear power plants.