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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Vladimir A. Babenko, Laszlo L. Jenkovszky, Volodymyr A. Romanov, Volodymyr N. Pavlovych, Oleg Ya. Vertsimakha
Nuclear Science and Engineering | Volume 133 | Number 3 | November 1999 | Pages 301-313
Technical Paper | doi.org/10.13182/NSE99-A2090
Articles are hosted by Taylor and Francis Online.
The results are presented of an investigation of the multiplying properties of lava-formed fuel-containing masses (LFCM); also, the possibility of developing ignition and dynamics of a self-sustaining chain reaction (SCR) in the LFCM of the destroyed Unit 4 of the Chernobyl nuclear power plant (the so-called Shelter) is discussed. The SCALE 4.3 computer code was used to calculate the multiplication factor, the neutron energy spectrum, the spatial distribution of the neutron flux density, etc., as functions of the water content in the LFCM for different system models. These results can help to determine the optimum placement of detectors in the rooms under the reactor. In addition, the dynamic of an SCR under the hypothetical condition that the filling of the LFCM by water leads to an excess multiplication factor over unity was considered. Such a treatment was performed for a simple model that takes into account the evaporation of water and an increase in temperature due to an energy release in the LFCM. The different modes of the LFCM behavior depending on the velocity of water filling are discussed.