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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.
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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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Latest News
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Paul W. Humrickhouse, Brad J. Merrill, Su-Jong Yoon, Lee C. Cadwallader
Fusion Science and Technology | Volume 75 | Number 8 | November 2019 | Pages 973-1001
Technical Paper | doi.org/10.1080/15361055.2019.1658464
Articles are hosted by Taylor and Francis Online.
In this work we consider some of the safety implications of using liquid metal (LM) plasma-facing components (PFCs) in future fusion reactors. Candidate LMs include lithium, tin, and tin-lithium alloys, and we consider a modified Fusion Nuclear Science Facility design with a dual-cooled lead-lithium blanket and fast-flowing LM first wall and divertor consisting of each of these aforementioned metals. Tin and tin-lithium PFCs are found to have little impact on the potential source terms, including tritium and activation product releases during an accident as well as tritium permeation losses during normal operation, relative to the lead-lithium blanket. For a lithium PFC, chemical reactivity and high tritium inventories are additional concerns. We outline some necessary safety precautions for lithium systems and review the relevant operating experience of sodium-cooled fission reactors. Design constraints to keep the tritium inventory low in such a lithium system are outlined, including in the tritium extraction system, which will have to rely on different techniques than envisioned for other LMs such as PbLi, Sn, and SnLi, which have a much lower tritium solubility than lithium. Development of such extraction systems is significant research and development needed prior to deployment of lithium PFCs.