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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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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.
Alex Galperin, Gilad Raizes
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 125-132
Technical Paper | Fission Reactor | doi.org/10.13182/NT97-A35319
Articles are hosted by Taylor and Francis Online.
The possibility exists of utilizing pressurized water reactor (PWR) power plants of current technology for efficient and cost-competitive incineration of excess plutonium. Several plutonium-based fuel cycle options were considered, i.e., pure 239Pu or reactor-grade plutonium as a fissile component and natural uranium or thorium as a fertile component of the fuel. A typical PWR was chosen as the base for detailed analysis and comparison of all investigated fuel cycle options. A series of calculations was carried out for each of the fuel cycle options generating “equilibrium” cycles of equal length. Results of the design analysis and comparison of main performance parameters were used to compare different fuel options. Material mass balances were calculated to evaluate the plutonium incineration potential of the considered options. A potential of efficient reduction of excess plutonium was demonstrated for all considered fuel options. The thorium-based fuel cycles were found especially effective for destruction of fissile isotopes of plutonium (>1000 kg/yr). This was partially compensated by the buildup of 233U isotope. One of the important conclusions of this work is that significant amounts of fissile plutonium may be incinerated in thorium-based cycles and that 233U may be denatured by addition of modest amounts of natural uranium. Preliminary economic evaluations indicate that plutonium incineration may be carried out in existing PWRs without economic penalty and may, therefore, present a viable alternative to other plutonium disposition methods.