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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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Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Samaneh Rakhshan Pouri, Supathorn Phongikaroon
Nuclear Technology | Volume 197 | Number 3 | March 2017 | Pages 308-319
Technical Paper | doi.org/10.1080/00295450.2016.1273730
Articles are hosted by Taylor and Francis Online.
Cyclic voltammetry is one of the most common electroanalytical methods for determining the thermodynamic and electrochemical behavior of a species in the eutectic molten salt. The diffusion coefficient, apparent standard potential, transfer coefficient, equilibrium potential, and other parameters can be determined through this method. This study focused on a development of an interactive reverseengineering method by analyzing available uranium chloride data sets (1 to 10 wt%) in a LiCl-KCl molten salt at 773 K under different scan rates to help improve and provide robustness in detection analysis. A principle method and a computational code have been developed by using electrochemical fundamentals and coupling various variables, such as the diffusion coefficients, formal potentials, and process time duration. In addition, a graphical user interface (GUI) through the commercial software Matlab was created to provide a controllable environment for different users. Results provide plots of current, potential, and concentration of each species as a function of time under various determined conditions. The GUI also displays the reversible and irreversible peaks, in a very short run time (around 2 min), with an adequately selected time interval of approximately 0.08 s and an ability to calculate the concentration of each species (e.g., U4+ and U3+) at any specified conditions.