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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
R. E. Maerker and F. J. Muckenthaler
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 423-433
Technical Paper | doi.org/10.13182/NSE67-A18281
Articles are hosted by Taylor and Francis Online.
Monte Carlo calculations have been carried out to determine the fast-neutron dose-rate distributions along the center lines of both a straight and a two-legged square concrete duct for a particularly demanding source geometry. The calculations incorporated doubly differential dose-albedo data for concrete which were previously reported. A comparison of the results of the calculations with those from a geometrically similar experiment shows good agreement, and places on a firm foundation the concept of treating the fast-neutron duct transmission problem as a reflection phenomenon at a point that is describable by the differential albedo properties of the walls.