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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
H. Shaked, D. R. Olander, and T. H. Pigford
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 122-130
Technical Paper | doi.org/10.13182/NSE67-A17814
Articles are hosted by Taylor and Francis Online.
The lattice diffusion coefficient of 133Xe in cast uranium monocarbide was measured by postirradiation anneal experiments in the temperature range 1000 to 2000°C. The experimental results were analyzed by a small-time solution of Fick's law in which the effect of depletion of the surface layer due to recoil was incorporated in the initial distribution. The diffusion coefficient of specimens consisting of large grains (700 to 1000μ) was best approximated by in the range 1000 to 2000'C. Specimens with small grains (20 to 150μ) exhibited the same diffusion coefficient as the large grain samples above 1500°C. Below 1500°C, diffusivities in small-grained specimens varied widely, indicating dependence on grain size and, hence, the existence of appreciable grain-boundary diffusion.