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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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August 2024
Latest News
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.
P. E. Reagan, J. G. Morgan and O. Sisman
Nuclear Science and Engineering | Volume 23 | Number 3 | November 1965 | Pages 215-223
Technical Paper | doi.org/10.13182/NSE65-A19554
Articles are hosted by Taylor and Francis Online.
The fission-gas release from pyrolytic-carbon-coated fuel particles during irradiation was studied for gas-cooled reactor application. Duplex-and triplex-type coatings on thorium-uranium carbide cores and on uranium carbide cores were tested at temperatures between 2000 and 2500°F (1093 and 1371 °C). Both types of coatings retained fission gas quite well up to about 20at.% heavy-metal burnup. Postirradiation examination revealed that the particles with the duplex coating were more susceptible to radiation damage (by the formation of a reaction zone at the core/coating interface) than were the particles with the triplex coating. This damage, however, did not affect the fission-gas release rates.