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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
H. G. Groehn
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 392-400
Heat Transfer and Fluid Flow | doi.org/10.13182/NT82-A32866
Articles are hosted by Taylor and Francis Online.
The effect of cross flow on the main coolant flow was studied at a two block test section on the model scale of 1:1. The cross flow was introduced through a wedge-shaped gap located between the two succeeding fuel blocks mentioned. The gap width varied from 1.85 to 6 mm. The entrance area for the cross flow was modified by the arrangement of blocking pieces around the circumference of the gap. The velocity distribution over the cross section of the fuel blocks and the pressure loss over the gap were measured. The experimental results allow the prediction of the flow reduction in each coolant channel of the fuel block depending on the transverse pressure gradient driving the cross flow.