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.
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Latest Journal Issues
Nuclear Science and Engineering
Fusion Science and Technology
Study indicates pilot facility could significantly reduce waste volumes
Waste disposal start-up Deep Isolation and fusion tech company SHINE Technologies have announced the completion of a collaborative study assessing the costs of disposing of radioactive byproducts from a pilot spent nuclear fuel recycling facility.
N. V. Kornilov, S. M. Grimes, T. N. Massey, C. E. Brient, D. E. Carter, J. E. O’Donnell, K. W. Cooper, A. D. Carlson, F. B. Bateman, C. R. Heimbach, N. Boukharouba
Nuclear Science and Engineering | Volume 194 | Number 5 | May 2020 | Pages 335-349
Technical Paper | doi.org/10.1080/00295639.2019.1702408
Articles are hosted by Taylor and Francis Online.
The n-p scattering angular distribution was measured with 14.9 MeV incident neutrons produced at the neutron facility of Ohio University. The traditional time-of-flight technique with neutron-gamma discrimination was applied for the measurement of the number and energy of scattered neutrons. The scattering angle varied from 20 to 65 deg (laboratory system) in 5 deg incremental steps corresponding to an ejectile energy range from 13.16 to 2.66 MeV. The efficiency of the neutron detectors was measured in the energy range 2 to 9 MeV relative to the 252Cf standard and was calculated using Monte Carlo methods in the 2 to 14 MeV energy range. Two methods of analysis were applied for experimental and simulated data: a traditional approach with a fixed threshold ~0.1MeVee and a dynamic threshold approach. The efficiencies determined by both methods are in excellent agreement for simulated and experimental results within the energy interval 2 to 9 MeV. The experimental (<9 MeV) and calculated efficiencies (>9 MeV) were applied for evaluation of the n-p scattering experimental result. The corrections for neutron attenuation in the “scatter-detector” were calculated with analytical formulas and by the Monte Carlo method. Additional minor corrections for edge effect, C(n,n’)3α background and dead time were also included. The present data agree with recent evaluations for the n-p angular distribution within about 1.6%. The current state-of-the-art of experimental uncertainties that can be realized for a neutron counting experiment were reached in this investigation. An additional correlation analysis allows us to conclude that the standard deviation connected with existing correlations may be the main component of the total uncertainty.