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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
V. Drüke, D. Filges, R. D. Neef, N. Paul, H. Schaal
Nuclear Science and Engineering | Volume 97 | Number 1 | September 1987 | Pages 37-52
Technical Paper | doi.org/10.13182/NSE87-A23494
Articles are hosted by Taylor and Francis Online.
Several fuel-loading concepts are proposed for high-temperature reactors of the pebble-bed type. A very promising one is the so-called OTTO (once through then out) loading scheme. Some of the intrinsic features of OTTO fuel loading are the axial nonsymmetrical power and neutron flux distribution with a pronounced maximum at the upper reactor core region. Since the neutron physics of OTTO cores will be very different from previous homogeneous fuel-loading schemes, detailed experimental and theoretical investigations of these objectives were performed at the critical facility KAHTER. Experimental and theoretical investigations have been carried out to determine critical masses, reaction rates, and control rod worths in the upper cavity and top reflector. Fast flux distributions in upper graphite reflectors were also measured to estimate graphite damage. The critical masses and keff’s are calculated using two- and three-dimensional code systems. The three-dimensional codes give keff values for the high-temperature gas-cooled reactor OTTO cores at zero burnup within a margin that is currently standard for these calculations. The agreement of measured and calculated reactivity worths of the top reflector rods is better than 2%.