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.
Sei-Hun Yun et al.
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 373-378
Materials Development & Plasma-Material Interactions | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12383
Articles are hosted by Taylor and Francis Online.
Experiments were conducted to obtain thermo physical properties of ZrCo and ZrCo hydride, which determine heat transfer phenomena in the hydrogen-ZrCo system. Heat capacity, thermal diffusivity and thermal conductivity of ZrCo and ZrCo hydride using Baotou ZrCo (China) are found to have U shaped curvatures with the temperature increase. In the temperature range of 300 - 500 K the thermal conductivity of ZrCoHx was found to be about 2/3 that of ZrCo and the initial hydrogen content of ZrCoHx used in this study was taken to be x=2.0.
