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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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.
K. P. Termaat, N. V. Kema
Nuclear Technology | Volume 38 | Number 3 | May 1978 | Pages 367-373
Technical Paper | Reactor | doi.org/10.13182/NT78-A32034
Articles are hosted by Taylor and Francis Online.
To obtain a longer power cycle length, the beginning-of-cycle excess reactivity of the reactor core must be increased. In the case of the Dodewaard reactor, this was done by raising the 235U enrichment of the fuel from 2.5 to 2.8%. To meet the shutdown margin criterion, the burnable poison, gadolinium, was added to 2 out of 36 fuel pins of each fresh fuel assembly. When a large number of these types of fuel assemblies are used to reload a reactor core, we must know the reactivity behavior of the hot operating core, as well as the variation in shutdown margin of the cold core as a function of burnup. By using a relatively simple analytical model, a reasonable prediction of these two phenomena could be made as shown by comparison with actual measurements and results of calculations with the FLARE computer code.