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.
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.
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
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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Registration is open for NRC’s RIC
The Nuclear Regulatory Commission has opened registration for its 35th annual Regulatory Information Conference (RIC 2023) The conference, themed “Navigating the Nuclear Future,” will be held March 14–16 in North Bethesda, Md., and will be the first in-person RIC since 2019, although the event will also be accessible virtually.
Register now. Registration, which is required to attend, can be completed by filling out the conference registration online form. The conference is free to the public.
Bastien Faure, Pascal Archier, Jean-François Vidal, Laurent Buiron
Nuclear Science and Engineering | Volume 192 | Number 1 | October 2018 | Pages 40-51
Technical Paper | doi.org/10.1080/00295639.2018.1480190
Articles are hosted by Taylor and Francis Online.
Fast resolution of the Boltzmann transport equation over a nuclear reactor core presupposes the definition of homogenized and energy-collapsed cross sections. In modern sodium fast reactors that rely on heterogeneous core designs, anisotropy in the neutron propagation cannot be neglected, so three-dimensional (3D) models should be used to efficiently compute those effective cross sections. In this paper, the 2D/1D approximation is carried out to overcome computationally expensive 3D calculations while preserving consistent angular representations of the neutron flux. An iterative procedure is defined to solve the 2D/1D equations and produce coarse group homogenized cross sections that account for 3D transport effects. Accuracy of the algorithm is tested on a realistic model of the ASTRID core showing very good results against Monte Carlo simulations for all neutronic parameters (eigenvalue, sodium void worth, and fission map distribution).