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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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.
Todd K. Campbell, Edgar Robert Gilbert, Cheryl Knox Thornhill, Bernard J. Wrona
Nuclear Technology | Volume 84 | Number 2 | February 1989 | Pages 182-195
Technical Paper | Fuel Cycle | doi.org/10.13182/NT89-A34186
Articles are hosted by Taylor and Francis Online.
To support dry storage technology, oxidation tests were conducted with light water reactor spent fuel. The initial rate of weight gain for spent fuel was up to 50 times greater than the initial rate for nonirradiated pellets. Spent fuel formed measurable U4O9+x particulates at weight gains significantly higher than those at which the nonirradiated pellets formed U3O8 powder. Initial test results on three types of pressurized water reactor (PWR) spent fuel indicated that fuel type had a significant influence on weight gain. Additional tests were performed at temperature levels from 135 to 230°C on fuel with burnups from 8 to 34 GWd/ tonne U irradiated in five different reactors. The tests were conducted in static air at controlled moisture levels in a 105 R/h gamma field. In the 230°C tests, weight gains for PWR and boiling water reactor (BWR) fuels exceeded 4 wt% after 4000 h of exposure. Powder formation time on BWR fuels increased with increasing burnup; weight gain magnitudes were independent of fuel burnup.
