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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
Harry M. Ferrari
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 503-512
Technical Paper | doi.org/10.13182/NSE63-A18440
Articles are hosted by Taylor and Francis Online.
The mechanism and kinetics of nitrogen release from UO2 pellets containing high nitrogen impurities have been investigated at elevated temperatures. A combination of metallographic and x-ray analyses showed that nitrogen present in the UO2 exists as a second phase in the form of uranium nitrides. The kinetics of nitrogen release were measured at temperatures of 1000, 1200, 1400, and 1600°C and the mechanism of release was determined to be controlled by the diffusion of nitrogen through the UO2 lattice. The variation in nitrogen pressure upon heating a UO2 fuel element to elevated temperatures was studied. The data showed that a reversible equilibrium pressure-temperature relationship did not exist between the nitrides in the UO2 and the nitrogen gas above it as occurs with pure uranium nitrides. The quantity of nitrogen which will be released in a UO2 fuel element is determined by the kinetics of diffusion of nitrogen through the UO2 lattice and may be computed for any given fuel element design utilizing a diffusion model similar to one used for computing release of fission gases.