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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
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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.
S. Kumar, C. S. Viswanadham, S. Bhattacharya, S. B. Roy, K. Bhanumurthy, G. K. Dey
Fusion Science and Technology | Volume 65 | Number 2 | March-April 2014 | Pages 199-204
Technical Paper | doi.org/10.13182/FST13-650
Articles are hosted by Taylor and Francis Online.
India is a partner in ITER and plans to test its lead lithium ceramic blanket test blanket module. This component is embedded with a large number of cooling channels of different profiles and, therefore, is a challenging component to fabricate. Cooling channel reconstruction by employing high-power laser welding provides a promising scheme to fabricate this component. Cooling channel reconstruction was demonstrated in American Society for Testing and Materials A387 Gr91 steel using high-power CO2 laser welding. A scheme for fabrication of scale models of different subcomponents, like the first wall (FW) and inner back plate, and assembly of the two subcomponents employing the cooling channel reconstruction scheme was demonstrated. The steady-state temperature field around the weld joint was computed using the welding and heat treatment simulation solution package SYSWELD. These weld joints were characterized for microstructure at different length scales, microhardness, and room-temperature tensile properties. This paper presents the scheme used for cooling channel reconstruction and the results of the weld joint characterization. The scheme for fabrication of the scale model of the FW, the inner back plate, and joining of the two subcomponents using the cooling channel reconstruction approach is also described in this paper.