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
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
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
R. E. Maerker, F. J. Muckenthaler
Nuclear Science and Engineering | Volume 52 | Number 2 | October 1973 | Pages 227-246
Technical Paper | doi.org/10.13182/NSE73-A28192
Articles are hosted by Taylor and Francis Online.
A description is presented of an experiment which provides verification of the accuracy of the available neutron cross sections for use in transport calculations of deep penetration of neutrons through up to 3 ft of iron and 18 in. of stainless steel. Calculations of the experiment were performed with a special version of the MORSE multigroup Monte Carlo code which uses point total cross sections. Comparison of the calculations using the new MAT 4180-Mod 1 iron cross-section set with experiment indicates that the absolute neutron leakage spectra above thermal energies arising from scattering that penetrate up to 1 ft of iron or 18 in. of stainless steel can be calculated to within ∼20%, and that the total neutron leakage above thermal energies penetrating up to 3 ft of iron can also be calculated to about the same accuracy.