ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
D. E. Cullen, N. P. Kocherov, P. M. McLaughlin
Nuclear Science and Engineering | Volume 83 | Number 4 | April 1983 | Pages 497-504
Technical Note | doi.org/10.13182/NSE83-A18654
Articles are hosted by Taylor and Francis Online.
Calculated spectrum-averaged cross sections are presented for all of the reactions in the International Reactor Dosimetry File (IRDF-82) using the ten benchmark neutron fields that were distributed with IRDF-82. Comparisons to experimentally measured spectrum-averaged cross sections are presented for the 252Cf and 235U thermal fission spectra. This comparison shows that the difference between the measured and calculated spectrum averages is still much larger than the experimentally quoted uncertainties. This indicates that more precise knowledge of these spectra and further evaluations are still needed.
