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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
History in the making: D&D begins on Three Mile Island-2
Constellation Energy has announced that it will seek to restart Unit 1 of the Three Mile Island nuclear power plant in Pennsylvania as part of an agreement with Microsoft to power that company’s data centers. Given the growing interest by tech companies in using clean, reliable nuclear power to meet their growing energy demands, the September 20 announcement to reopen TMI-1, which was shut down and defueled in 2019, was not a huge surprise.
Mark L. Crowder, James E. Laurinat, John A. Stillman
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Pages 309-313
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT11-A13305
Articles are hosted by Taylor and Francis Online.
A straightforward method to determine the tritium content of Zircaloy-2 cladding hulls via oxidation of the hulls and capture of the volatilized tritium in liquids has been demonstrated. Hull samples were heated in air inside a thermogravimetric analyzer (TGA). The TGA was rapidly heated to 1000°C to oxidize the hulls and to release absorbed tritium. To capture tritium, the TGA off-gas was bubbled through a series of liquid traps. The concentrations of tritium in bubbler solutions indicated that nearly all of the tritiated water vapor was captured. The average tritium content measured in the hulls was 19% of the amount of tritium produced by the fuel, according to ORIGEN2 isotope generation and depletion calculations. Published experimental data show that there is an initial, nonlinear oxidation rate for Zircaloy-2 followed by a faster, linear rate after "breakaway" of the oxide film and that the linear rate follows an Arrhenius model. This study demonstrates that the linear oxidation rate of Zircaloy samples at 974°C is faster than predicted by the extrapolation of data from lower temperatures.