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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
October 2025
Nuclear Technology
September 2025
Fusion Science and Technology
Latest News
NNSA awards BWXT $1.5B defense fuels contract
The Department of Energy’s National Nuclear Security Administration has awarded BWX Technologies a contract valued at $1.5 billion to build a Domestic Uranium Enrichment Centrifuge Experiment (DUECE) pilot plant in Tennessee in support of the administration’s efforts to build out a domestic supply of unobligated enriched uranium for defense-related nuclear fuel.
Bryce L. Shriver, Thomas G. Hook
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 113-117
Technical Paper | Material | doi.org/10.13182/NT83-A33148
Articles are hosted by Taylor and Francis Online.
The operation of some early-generation light water reactors may be limited by the irradiation-induced embrittlement of their reactor vessels. Additional nondestructive methods of measuring the actual embrittlement are desirable to support limits placed on the operation of these vessels. Previous studies have indicated that the increase in microhardness with irradiation may correlate with shifts in the ductile-to-brittle transition temperature. However, the previous research did not consider variations in the test temperature to determine whether it affects the correlation with transition temperature or whether microhardness may correlate with the fracture energy outside the transition region. The Vickers microhardness measurements were made at eight temperatures from -195 to 90°C (-320 to 200°F) by holding the samples in a liquid bath during the application of the test load. Both unirradiated and irradiated samples were evaluated for the three A533-B steels. These tests indicate that the Vickers hardness may correlate with the strength and ductility of unirradiated steels. In addition, both the change in microhardness and the shift in test temperature at a constant hardness may correlate with the shift in transition temperature caused by irradiation.