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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
Herbert Rief
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 83-89
Technical Paper | doi.org/10.13182/NSE61-A25934
Articles are hosted by Taylor and Francis Online.
A Monte Carlo code is used to calculate the fast effect in both homogeneous and heterogeneous systems. The following results are obtained: for an infinite block of natural uranium, δ28 = 0.39, ∈ = 1.247; for an infinite block of beryllium, ∈ = 1.078; for beryllium oxide, ∈ = 1.046. In addition, results are given for homogeneous mixtures of uranium and beryllium. Calculations have also been carried out for uranium-water lattices and compared with experimental results for slightly enriched uranium rods and slabs, and uranium oxide rods. Other results show the increase in ∈ when uranium fuel elements are surrounded by beryllium cladding of varying thickness.
