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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.
David Blanchet, Bruno Fontaine
Nuclear Science and Engineering | Volume 177 | Number 3 | July 2014 | Pages 260-274
Technical Paper | doi.org/10.13182/NSE13-59
Articles are hosted by Taylor and Francis Online.
The current design studies on sodium-cooled fast reactors (SFRs) are breaking with the past since they are guided by a new set of design criteria arising from the objectives of Generation IV reactors. The new safety requirements lead to designing reactors with breakeven breeding cores because in terms of reactivity control, they minimize the need to limit the consequences of an inadvertent control rod withdrawal event. Furthermore, as the reactivity control needs are low, a breakeven core enables the use of absorbing materials with reduced efficiency (natural boron, hafnium, etc.), which may be less costly than enriched boron. However, control rods designed with low absorbing materials may present the disadvantage of a nonnegligible loss of efficiency due to their consumption under irradiation. This paper presents a methodology to accurately calculate and to analyze the impact of this consumption on reactivity control.