ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
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Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
X.-N. Chen, D. Zhang, W. Maschek
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 275-280
Modeling and Simulations | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13432
Articles are hosted by Taylor and Francis Online.
This paper is a theoretical study of a radial standing wave, which can be applied in the so-called traveling wave reactor (TWR). Two-dimensional cylindrical core geometry is considered and the fuel is assumed to drift radially, which corresponds to a radial fuel shuffling scheme in practice. A one-group diffusion equation coupled with burn-up equations is set up, where the burn-up solution is obtained numerically. The uranium-plutonium (U-Pu) conversion cycle with pure 238U as fresh fuel is considered under conditions of a typical sodium cooled fast reactor with metallic uranium fuel loaded. The asymptotic problem is solved by a time-stepping iteration scheme and the radial standing wave solution is obtained together with certain eigenvalue keff.The neutron flux, the neutron fluence and the net neutron generation cross section are presented and discussed for the inward fuel drifting motion.