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
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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Latest News
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.
J. J. H. Brouwers
Nuclear Technology | Volume 39 | Number 3 | August 1978 | Pages 311-322
Technical Paper | Isotopes Separation | doi.org/10.13182/NT78-A32061
Articles are hosted by Taylor and Francis Online.
The gas circulation in a gas centrifuge due to temperature differences, differential rotation and injection, and removal of fluid at the ends, as well as due to temperature gradients at the cylinder wall is treated analytically. The motion consists of a small perturbation on a state of isothermal rigid body rotation. Linear analysis of conservation of mass, momentum, and energy and the perfect gas law leads to the definition of several vertical layers and regions at various radii: a Stewartson layer near the wall where viscosity and heat conduction are important to allow the thermal and kinematic conditions at the wall; an inviscid region; and an inner layer adjusting the inviscid flow to a diffusion-controlled center region where, due to low density, mass fluxes are negligible. The axial motion in these layers and regions is short-circuited in Ekman layers at the ends. The solutions for the flow field are used to calculate the maximum attainable separative power of a countercurrent gas centrifuge for uranium enrichment. It appears that the separative power is less than Dirac’s figure, the difference being primarily determined by the width of the diffusion-controlled region in the center of the rotor. The difference increases with circumferential velocity and cylinder length and decreases with cylinder radius and gas pressure at the wall.