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Division Spotlight
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.
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!
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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.
Rebecca Pachuau, B. Lalremruata, N. Otuka, L. R. Hlondo, L. R. M. Punte, H. H. Thanga
Nuclear Science and Engineering | Volume 187 | Number 1 | July 2017 | Pages 70-80
Technical Paper | doi.org/10.1080/00295639.2017.1291053
Articles are hosted by Taylor and Francis Online.
Recently, we measured the 70Zn(n,γ)71Znm activation cross sections using the 7Li(p,n)7Be neutron source for 2.0 MeV < Ep < 3.7 MeV. Since the time-of-flight and multiple foil activation techniques cannot be applied due to the continuous beam structure and weak neutron flux at the facility, we have to rely on calculated neutron energy spectra for data reduction procedure. There are existing Monte Carlo–based codes such as Protons In Neutrons Out (PINO) and SimLiT for calculation of 7Li(p,n)7Be neutron source spectra at these energies. However, these two codes predicted different neutron spectra at these energy regions. We therefore decided to study the thick and thin target 7Li(p,n)7Be neutron spectra from the reaction threshold to the three-body breakup threshold by deterministic calculation. The predicted neutron spectra near threshold were validated by experimental neutron spectra. Our neutron spectra were compared with those predicted by PINO and SimLiT. Our neutron spectra at Ep = 2.8 and 3.5 MeV agree perfectly with those predicted by SimLiT but not with those predicted by PINO.
