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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Nuclear new build procurement considerations
It may seem counterintuitive, but the best time to enhance the ability to support operations and maintenance for a new plant is before construction starts. This is one of many lessons learned by the currently operating nuclear fleet. As construction and startup of many nuclear facilities was completed, it quickly became evident that the ability to efficiently support operations and maintenance was limited. Most of the information necessary to establish and manage procurement of spare and replacement items, maintenance, and configuration of the facilities was unavailable and had to be gathered on a case-by-case, “on-demand” basis. Absence of necessary information and the associated challenges resulted in the need for staff augmentation and multiyear-long projects to develop equipment bills of material and maintenance programs and to perform technical evaluations for the huge quantities of spare and replacement items being requested.
Carolyn Coyle, Emilio Baglietto, Charles Forsberg
Nuclear Science and Engineering | Volume 194 | Number 8 | August-September 2020 | Pages 782-792
Technical Paper | doi.org/10.1080/00295639.2020.1723993
Articles are hosted by Taylor and Francis Online.
Liquid salts have become more attractive as coolants for low-carbon power generation due to needs for high-temperature heat and affordable energy storage. Of particular interest are halide salts utilized in fluoride-salt-cooled high-temperature reactors, molten salt reactors, and high-magnetic-field fusion machines, as well as in concentrated solar power systems. Because of their high-temperature operation and semitransparent nature, the liquid salts in these designs may experience the effects of participating media radiative heat transfer (RHT). While some work has been conducted on measuring the thermophysical properties of these fluids, there is currently very little known about their radiative properties.
Here, we present the initial results of a two-part methodology to enhance RHT understanding and improve modeling in high-temperature liquid salts. First, an experimental apparatus designed to measure liquid chloride and fluoride salt absorption coefficients by Fourier transform infrared spectroscopy was completed and validated with water measurements. Second, computational fluid dynamics (CFD) simulations were run to determine the contribution of thermal radiation to the overall heat transfer for flow between parallel plates. This geometry was used to verify code accuracy and investigate requirements for absorption coefficient spectral banding. Future work will be to complete halide salt absorption measurements and couple them to the established CFD methods to identify geometries and temperatures where RHT is significant and enable prediction of heat transfer in such systems.