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 8–12, 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
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Anfield Energy to start construction of Utah uranium mine
British Columbia-based Anfield Energy has scheduled a groundbreaking on November 6 at its uranium and vanadium Velvet-Wood mine, located in southeastern Utah’s Lisbon Valley. According to Corey Dias, the company’s CEO, it will be "more than a groundbreaking—it’s a bold declaration of Anfield’s readiness to help fuel the American nuclear renaissance.”
R. L. Currie, P. B. Parks, J. L. Jarriel
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 356-362
Technical Paper | Reactor | doi.org/10.13182/NT71-A30984
Articles are hosted by Taylor and Francis Online.
Subcritical multiplication constants have been derived from static and pulsed measurements for arrays of large, hollow cylinders of uranium-aluminum alloy. The cylinders were of two types: 11.21-cm-i.d., 20.07-cm-o.d. bare 235U-Al alloy castings and 10.07-cm-i.d., 12.27-cm-o.d. Alclad “logs” extruded from the castings. The alloy was 9.985 wt% enriched uranium (92.2% 235U) in aluminum. These measurements extended previous benchmark experiments with small diameter rods of lower enrichment into the region of larger diameters and higher enrichments. The transport diffusion theory codes MGBS-TGAN overestimated the values of keff for the arrays tested by 7 to 12%. The more sophisticated Monte Carlo code KENO was more accurate, with errors less than 5%.