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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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.
Liaquat Ali Khan, Nasir Ahmad
Nuclear Technology | Volume 119 | Number 2 | August 1997 | Pages 201-210
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35387
Articles are hosted by Taylor and Francis Online.
The effect of operating cycle and fuel burnup on the isotopic composition and decay characteristics of irradiated nuclear fuel has been investigated using a standard computer code, KORIGEN. The parameters studied include isotopic compositions of actinides; activities due to the actinides, fission products, and light elements; decay heat; and the spontaneous fission neutron source. Calculations have been performed for a typical swimming pool-type research reactor, using materials test reactor-type low-enriched uranium fuel, for four different operating cycles. A fuel burnup range of 5 to 35% has been considered. The cooling time ranged from a fraction of a second to thousands of years. Results indicate that the amount of plutonium produced is strongly dependent on fuel burnup. It is not significantly affected by the operating cycle. The operating history of the reactor has a strong influence on fission product inventory and decay heat. The main contributors to activity and decay heat for the first two to three centuries are fission products; thereafter, actinides are the main contributors. The activity and decay heat drop drastically during the first day after shutdown. Both alpha activity and the spontaneous fission neutron source are strongly dependent on the operating cycle and fuel burnup. These increase with an increase in the fuel burnup but decrease for a longer power-on cycle.