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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
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!
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Nuclear Science and Engineering
March 2025
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February 2025
Latest News
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
G. B. Hiremath, V. P. Singh, N. H. Ayachit, N. M. Badiger
Nuclear Science and Engineering | Volume 198 | Number 9 | September 2024 | Pages 1806-1816
Research Article | doi.org/10.1080/00295639.2023.2270742
Articles are hosted by Taylor and Francis Online.
The Ti-Nb-Fe-Cr alloys are used in various fields, such as nuclear radiation shielding, cladding material in nuclear reactors, and implants in the medical field. It is one of the best materials for biomedical applications as it is biocompatible, is corrosion resistant, and has good mechanical properties. As nuclear radiation emanates from various sources in a nuclear reactor, the behavior of this alloy with the interaction of gamma and neutrons has not been well studied. In the present investigations, the interaction of gammas and neutrons with Ti-27Nb-7Fe-xCr (x = 0, 2, 4, 6, and 8 wt%) alloys is studied in order to understand the radiation shielding properties and their usefulness in biomedical applications. Gamma-ray–interaction parameters such as MAC, HVL, MFP, Zeff, Zeq, Neff, and multilayer energy absorption buildup factor (MLEABF) are estimated using EpiXs, PyMLBUF, and NGCal software in the energy range of 1 keV to 15 MeV. The multilayer buildup factor (MLBF) is calculated for cortical bone and for alloys with varying Cr concentrations. Comparison of the MLBF values of alloys with cortical bone shows that in the lower-energy region as well as the higher-energy region above 0.5 MeV, alloys and cortical bone yield the same values, indicating that the alloys behave as cortical bone in this energy region. Mass attenuation factors (MAFs) of thermal and fast neutrons are also calculated for various elastic modulus values of selected alloys at thermal and fast neutrons. It is found that the elastic modulus increases with increasing MAF values of both fast and thermal neutrons. By increasing the Cr content in the Ti-27Nb-7Fe alloy, the elastic modulus decreases. The relationship between the MAF of neutrons and the elastic modulus of the alloy is established for the first time.
