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
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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
September 2024
Nuclear Technology
August 2024
Fusion Science and Technology
Latest News
Taking shape: Fusion energy ecosystems built with public-private partnerships
It’s possible to describe fusion in simple terms: heat and squeeze small atoms to get abundant clean energy. But there’s nothing simple about getting fusion ready for the grid.
Private developers, national lab and university researchers, suppliers, and end users working toward that goal are developing a range of complex technologies to reach fusion temperatures and pressures, confounded by science and technology gaps linked to plasma behavior; materials, diagnostics, and electronics for extreme environments; fuel cycle sustainability; and economics.
Roberto Orsi
Nuclear Science and Engineering | Volume 157 | Number 1 | September 2007 | Pages 110-116
Computer Code Abstract | doi.org/10.13182/NSE07-A2716
Articles are hosted by Taylor and Francis Online.
This paper aims to stimulate research and to focus the attention of deterministic radiation transport code developers and users on further methodologies in transport analysis that some recent additions to the code package BOT3P potentially make possible in structured Cartesian or cylindrical mesh grids simulating complex geometries. In particular, BOT3P Version 5.0 can compute the possible area/volume error of material zones due to the stair-cased geometrical representation and automatically correct material densities in order to conserve masses, as described in a previous BOT3P paper published in Volume 154, Number 2 of Nuclear Science and Engineering to which the present one is logically and strictly related. When calculating areas and volumes refinements or when reducing the problem sizes of a voxelized geometry, typical of medical applications, BOT3P generates binary files that store also a fine submesh grid for each coarse cell at material interfaces. These files were originally conceived only for density correction computation and plotting purposes. However, the availability of such cell data intuitively suggests multistep transport analysis approaches that may combine detailed solutions at material interfaces with acceptable problem sizes and computational times. Reaching this appealing target could let deterministic codes based on structured mesh grid successfully deal with any challenging geometry problem. That might be particularly useful in medical and reactor applications.