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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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Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
A.G. Heics, W.T. Shmayda
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 1030-1034
Material; Storage and Processing | doi.org/10.13182/FST92-A29887
Articles are hosted by Taylor and Francis Online.
Zirconium cobalt (ZrCo) is being evaluated as an alternative to uranium for tritium storage. The pumping speed and pressure-composition-temperature isotherm profiles for the ZrCo hydrogen and tritium systems were measured to determine isotopic differences and the effect of He-3 induced aging on ZrCo performance. Hydrogen is pumped by ZrCo at a slightly faster rate than tritium under identical test conditions. The ZrCo/H2 system has a slightly lower equilibrium pressure compared to the ZrCo/T2 system at corresponding compositions. Aging ZrCo with tritium for 57 days appears to have no noticeable effect on the tritium pumping speed relative to virgin ZrCo.