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
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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Constellation seeks rezone for property adjacent to Illinois plant
While no development details have been released, Constellation is asking to rezone 658.8 acres of land it owns around the Byron nuclear plant in Illinois for possible long-term use.
D. Wootan, R. Omberg, A. Casella, N. Lahaye, B. Mcdowell (PNNL), W. Stokes (Columbia Basin Consulting Group)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 36-44
The accident scenarios that need to be analyzed within Chapter 15 of a safety analysis report may vary significantly between advanced reactors and the light water reactors that compose the current commercial fleet. In anticipation of identifying scenarios of concern and developing methods for their analysis, correlations may be made to calculations and tests performed in support of the liquid metal and molten salt reactors that have been operated previously within the US. In this paper, we discuss efforts made to compare Chapter 15 considerations for a proposed lead-bismuth cooled reactor to those developed previously for the Fast Flux Test Facility (FFTF) and the GE-Hitachi PRISM reactor. Comparisons were also made with Beyond Design Basis Accidents for FFTF.