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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
D. O. Campbell, A. P. Malinauskas, W. R. Stratton
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 111-119
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Safety | doi.org/10.13182/NT81-A32615
Articles are hosted by Taylor and Francis Online.
It is commonly assumed that the chemical form of fission product iodine that escapes from the core of a light water reactor under accident conditions is the elemental form. Experimental evidence is presented that indicates that this assumption is incorrect; instead, a metal iodide (probably cesium iodide) is the chemical form that escapes from the fuel. Moreover, since transport through the primary system necessarily occurs under chemically reducing conditions, a change in valence of the iodine is not possible until the oxidizing conditions characteristic of reactor containment buildings are encountered. However, it is also demonstrated that elemental iodine cannot be a dominant form if, as occurred at the Three Mile Island reactor, the iodide contacts water and is transported into the containment building in aqueous solution.