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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Nuclear Science and Engineering
June 2025
Nuclear Technology
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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
Joel Weisman
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 465-469
Technical Note | Reactor | doi.org/10.13182/NT72-A16044
Articles are hosted by Taylor and Francis Online.
Experimental data have shown a high resistance to cross flow in the presence of large axial flows. This phenomenon may be explained by use of a full lateral momentum balance. Application of the momentum balance principle shows that interchannel cross flow at any given level depends on the cross flow at the lower level in addition to the local pressure gradient. This revised procedure for calculation of cross flow should eventually lead to improved estimation of core wide flow redistribution in open lattice cores.