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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
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Latest News
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
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%.