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.
Explore membership for yourself or for your organization.
Conference 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
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
New coolants, new fuels: A new generation of university reactors
Here’s an easy way to make aging U.S. power reactors look relatively youthful: Compare them (average age: 43) with the nation’s university research reactors. The 25 operating today have been licensed for an average of about 58 years.
L. F. Hansen, J. D. Anderson, R. J. Doyas, R. J. Howerton, T. Komoto, C. M. Logan, C. Wong, J. L. Kammerdiener
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 345-348
Technical Note | doi.org/10.13182/NSE74-A23461
Articles are hosted by Taylor and Francis Online.
The neutron spectra emitted from 2 and 4 mean-free-paths of concrete irradiated by 14-MeV neutrons have been measured between 14 and 2 MeV using the sphere transmission and time-of-flight techniques. The spectra have been calculated with the Monte Carlo neutron transport code TART using the ENDL Livermore neutron library and the ENDF/B-III neutron library. From the comparison between measurements and calculations, it was inferred that the nonelastic cross section for oxygen in the ENDL library was too large. A revision of the cross sections for 14- and 14.6-MeV neutrons was carried out and resulted in very good agreement between measurements and calculations.