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
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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.