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Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Fusion Science and Technology
Latest News
Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
G. Tsotridis, I. Goded
Fusion Science and Technology | Volume 26 | Number 1 | August 1994 | Pages 7-16
Technical Paper | First-Wall Technology | doi.org/10.13182/FST94-A30297
Articles are hosted by Taylor and Francis Online.
Plasma-facing components in tokamak-type fusion reactors are subjected to intense heat loads during plasma disruptions. The influence of high heat fluxes on the depths of heat-affected zones on Type 316 stainless steel with different sulfur impurities was studied for a range of energy densities and disruption times. It was demonstrated in small beam simulation experiments that under certain conditions, impurities through their effect on surface tension create convective flows, hence exercising a determining influence on the flow intensities and the resulting depth of molten layers. When a CO2 laser is used as a heat source, the role of impurities diminishes, due to high temperatures on the surface of the specimens, and all types of stainless steel behave like pure material. However, by using an alternative heat source that produces lower surface temperatures, e.g., tungsten inert gas, the stainless steel containing high sulfur produces much higher melting zone thicknesses compared with the low sulfur steels. Comparison between experimental results and existing theoretical predictions reveal significant differences in the depths of the melt layers.