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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.
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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
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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.
H.-W. Bartels
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 544-549
Safety; Measurement and Accountability; Operation and Maintenance; Application | doi.org/10.13182/FST92-A29803
Articles are hosted by Taylor and Francis Online.
A significant fraction of the tritium inventory of a fusion plant will be in the elemental form HT. A simple model is proposed to calculate early doses following an HT release. The dose is not dominated by the primary HT plume but by deposition of HT into the soil, subsequent oxidation to HTO by microorganisms and the following reemission of HTO. The difficulty of calculating HTO concentrations from a large area source is solved by defining a reemission velocity. All data available from the large scale release experiments in France (1986) and Canada (1987) are used to fit this parameter. With typical worst case conditions one gets an early dose of 0.04 Sv/kg-T as HT at 1000 m distance from the source, building wake effects included. This model can also be used to calculate HTO-release doses and predicts 0.6 Sv/kg-T as HTO for the same worst case condition. About 20 % of this dose is caused by reemission of HTO deposited into the soil. The accuracy of the model is estimated to be a factor of 2 – 2.5 up and down.