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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Nuclear Science and Engineering
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Nuclear Technology
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May 2025
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.
Taichi Matsumura, Ryuji Nagaishi, Jun-ichi Katakura, Masahide Suzuki
Nuclear Science and Engineering | Volume 192 | Number 1 | October 2018 | Pages 70-79
Technical Paper | doi.org/10.1080/00295639.2018.1493856
Articles are hosted by Taylor and Francis Online.
In order to evaluate three-dimensional distributions of radionuclides with high precision from gamma-scanning profiles of adsorption vessels used for decontamination of radioactive water performed at severe accidents, gamma scanning of the submerged demineralizer system vessel at the Three Mile Island Unit 2 (TMI-2) accident was simulated in the axial and radial directions of real and cylindrical-shaped vessels using a Monte Carlo calculation code [Particle and Heavy Ion Transport Code System (PHITS)].
In the axial simulation, the true distribution of radioactive 137Cs in the zeolite packed bed of the vessel was successfully evaluated when a correction function derived from a virtual constant distribution of 137Cs was applied to the reported gamma-scanning profile. In the radial simulation, the virtual disk-formed and shell-formed sources of 137Cs displaced in the packed bed were clearly observed from the top and bottom views of the vessel. This new radial gamma scanning indicates that the radial localization of 137Cs could be well observed by measuring the gamma ray from the top view of the vessel during storage. Further, the radial gamma scanning from the side view and whether or not the radial localization of 137Cs can be confirmed in the normally existing gamma-scanning room were examined.