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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Mar 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
ANS 2025 election is open
The American Nuclear Society election is now open. Members can vote for the Society’s next vice president/president-elect and treasurer as well as six board members (four U.S. directors, one non-U.S. director, and one student director). Completed ballots must be submitted by 1:00 p.m. (EDT) on Tuesday, April 15, 2025.
Yoshihiko Kaneko, Fujiyoshi Akino, Yoshiro Suzuoki, Kenji Kitadate, Ryosuke Kurokawa,Kinji Koyama
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 105-116
Technical Note | doi.org/10.13182/NSE74-A23974
Articles are hosted by Taylor and Francis Online.
Neutron diffusion coefficients were measured in square lattices of aluminum channels in light water in both the axial and the radial directions by the pulsed neutron technique. The diameter of the channels was 15 mm and the pitch of the lattice was 19 or 24 mm. Good agreement was observed between the experimental values of the axial diffusion coefficient, Da, and those calculated by the two-dimensional discrete Sn method. In this calculation, the value of the diffusion coefficient was interpreted as the slope of the decay constant as a function of the geometrical buckling in the axial direction of the channels. Also, the measured values of the radial diffusion coefficients agreed well with those calculated by the well-known Benoist practical formulas. The relation between the extrapolation distance and the effective transport length in the axial direction, ℓa and 3Da/V was numerically investigated. The ratio of the former to the latter is found to be considerably higher than the value of 0.71 used hitherto.