ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Latest News
Atomic Museum marks 20 years of education
The National Atomic Testing Museum, better known as the Atomic Museum, is celebrating its 20th anniversary this year. Located in Las Vegas, Nev., the museum was established in 2005 to preserve the legacy of the Nevada Test Site, now called the Nevada National Security Sites.
Deanne Dickinson
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 265-277
Technical Paper | Chemical Processing | doi.org/10.13182/NT75-A24428
Articles are hosted by Taylor and Francis Online.
Monte Carlo calculations for pipe intersections containing highly enriched, concentrated uranyl nitrate solution and reflected by a concrete room provide safe pipe diameters for a range of room sizes. The pipe-wall material (steel, aluminum, or Plexiglas) has a small effect on keff for 0.125-in.-thick pipes. Replacing the uranyl nitrate solution by uranyl fluoride results in a large increase in keff, and using plutonium nitrate (3% 240Pu) lowers keff Reflector savings curves for water and for concrete around an infinite cylinder of uranyl nitrate solution show that thick concrete is a much better reflector than an equal thickness of water. The calculational data are summarized in the form of a table and a set of rules for the use of the table in the calculation of safe dimensions for a system of intersecting pipes. This method is also applicable to plutonium systems if the plutonium contains at least 3 wt% 240Pu and no 241Pu.