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Division Spotlight
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.
Meeting Spotlight
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.
A. Ibrahim, D. L. Henderson, L. A. El-Guebaly, P. P. H. Wilson, M. E. Sawan, ARIES Team
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 726-730
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A8994
Articles are hosted by Taylor and Francis Online.
The effects of neutron streaming through the divertor He-access pipes of the ARIES compact stellarator fusion power plant on the shielding performance of its components were investigated in this analysis. A 3-D analysis for the most promising design of the He-access pipe with shielding plug and inserts indicated that neutron attenuation through the shielded pipe is not sufficient to eliminate the issue of neutron streaming. The results show that the damage exceeded the limits near the pipe for the manifold, vacuum vessel, and magnet. Precautions should be taken that include changing the pipe design and orientation, avoiding rewelding the manifold and vacuum vessel near the pipe, and/or relocating the magnet away from the pipe. The neutron flux behind the pipe is excessive, mandating additional local shield (∼1 m) to protect the externals.