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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Sergey I. Belousov, Krassimira D. Ilieva
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 239-244
Technical Paper | doi.org/10.13182/NSE97-A24477
Articles are hosted by Taylor and Francis Online.
A new adjoint synthesis (ASYNT) method is proposed for synthesizing a three-dimensional solution from two- and one-dimensional solutions of the adjoint neutron transport equation. Its correctness and fast run ability are appropriate for evaluating neutron irradiation for the VVER/pressurized water reactor pressure vessel—especially for surveillance sites located out of the reactor core midplane.The solution axial dependence in circular cylindrical geometry is the main approximation used. The ASYNT method could be reduced to the traditional synthesis method by some supplementary approximations. The solution for every type of reactor is obtained by calculating the adjoint neutron transport equation only once for each surveillance site.