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
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
ANS Congressional Fellowship applications due
Applications for the Society’s Glenn T. Seaborg Congressional Science and Engineering Fellowship will be closing soon. Congressional Fellows can directly contribute to the federal policymaking process, working in either a U.S. senator’s or representative’s personal office or with a congressional committee. They will be responsible for supplying Congress with their expertise in nuclear science and technology, having a hand in the creation of new laws while gaining a deeper understanding of the legislative process.
Matthias Frankl, Rafael Macián-Juan
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 135-142
Technical Paper | doi.org/10.13182/NSE15-47
Articles are hosted by Taylor and Francis Online.
In radiation transport simulations, photonuclear processes still represent a rather new feature and are not as well established as neutron, electron, or other photon interactions. This study provides a benchmark for the photoneutron yields in C, Al, Cu, Ta, Pb, and U targets using the most current photonuclear cross-section library ENDF7U and the transport code MCNPX, v. 2.7. The isotopic material descriptions of C and Cu could be improved as more isotopes are available with the new library. The results were compared to experimental data provided by Barber and George [Phys. Rev., 116, 1551 (1959)]. In general, a good agreement can be observed although there seems to be a systematic underestimation in the calculated neutron yields.