ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
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.
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!
Latest Magazine Issues
Aug 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
October 2024
Nuclear Technology
Fusion Science and Technology
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.
Charles W. Townley, Neil E. Miller, Robert L. Ritzman, Richard J. Burian
Nuclear Science and Engineering | Volume 20 | Number 2 | October 1964 | Pages 171-179
Technical Paper | doi.org/10.13182/NSE64-A28931
Articles are hosted by Taylor and Francis Online.
Irradiation studies of Al2O3-, BeO, and pyrolytic-carbon-coated fuel particles have been carried out in the Battelle Research Reactor. Alumina-coated UO2 particles were found to be capable of a high degree of fission-gas retention during irradiations to at least 10 per cent bumup at temperatures up to 1100 C, The use of thick Al2O3 coatings (about 60 microns) and porous UO2 particles (about 80 per cent dense) was determined to be necessary to prevent cracking of the coatings at low temperatures. Coarse-grained beryllia coatings on UO2 particles have cracked during irradiations at 100 C and during thermal cycling in elevated temperature irradiations, but better performance is expected with fine-grained material. Failure of pyrolytic carbon coatings on UC2 particles was prevented in low-temperature irradiations by using thick coatings (>100 microns), but at elevated temperatures it was learned that the coatings had to be multilayered as well. Very promising results were obtained for pyrolytic-carbon-coated UO2 particles, good performance being observed over the temperature range of 100–1050 C.