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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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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.
Ernest R. Venerus and M. Necati Ozisik
Nuclear Science and Engineering | Volume 26 | Number 1 | September 1966 | Pages 122-130
Technical Paper | doi.org/10.13182/NSE66-A17195
Articles are hosted by Taylor and Francis Online.
Deposition of fission products from an isothermal laminar gas stream to the surfaces of a circular tube is theoretically investigated for a source releasing a radioactive precursor into the gas stream at a uniform rate at the origin. A slug velocity profile is assumed. In solving the partial differential equations of the problem, two different models are examined as boundary conditions to couple the equations. The first model, which is referred to as the Resistance Model, is applicable when the surface concentration of the deposited precursor is small or removal of particles from the surface is negligible; and it is equivalent to assuming a fictitious unknown resistance to mass transfer at the wall surface. The boundary value problem of mass transfer based on the resistance model has been solved for the transient conditions and analytical relations are derived for the concentration of fission products in the gas stream and on the tube surface. In the second model, which is referred to as the Transport Model, a more detailed account is taken of the actual physical transport process in the immediate vicinity of the conduit surface. The removal of precursor from the surface is related to the adsorption energy of the precursor and the temperature of the surface. Removal from the gas stream in the immediate vicinity of the conduit surface is described by a stream removal coefficient which is obtained from the kinetic theory of gases. The boundary value problem based on the transport model has been solved for the steady state condition only. The transport model has been applied to experiments on deposition of radioactive isotopes from laminar gas streams and adsorption energies for some radioactive isotopes are determined. Correlation of the transport model with experiments provides a useful means for obtaining the adsorption energies of radioactive isotopes on metal surfaces.