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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
June 2025
Nuclear Technology
Fusion Science and Technology
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.
Hideaki Matsuura, Takahiro Takaki, Yasuyuki Nakao, Kazuhiko Kudo
Fusion Science and Technology | Volume 39 | Number 3 | May 2001 | Pages 1167-1173
Technical Paper | doi.org/10.13182/FST01-A169
Articles are hosted by Taylor and Francis Online.
The radial profile of the neutron production rate in spherical inertial electrostatic confinement (SIEC) plasmas is numerically investigated for various device parameters, i.e., grid cathode current, grid voltage, etc. The electrostatic potential is obtained by solving the Poisson equation; and using the potential, the fuel-ion velocity distribution function is determined at each radial point. From the space-dependent velocity distribution function, the radial profile of the neutron production rate is evaluated. The influence of the broadness of the electron angular momentum distribution on the radial profile of the neutron production rate is also examined. It is shown that the height of the peak of the neutron production rate and its radial position are strongly influenced by the device parameters and the electron distribution.