ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Materials Science & Technology
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.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
Raphael Craplet, Joonhong Ahn
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 314-335
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A13478
Articles are hosted by Taylor and Francis Online.
A mathematical model for mass flow in a generic nuclear fuel cycle was developed. The model can describe various fuel cycle configurations (ranging from once-through to multiple recycling) and reactor types with several regions and batches. It can also be used as a submodel in a regional or global fuel cycle system. Recursive equations for the fuel composition at each point of the cycle were obtained. For specific simplified cases, nonrecursive and equilibrium equations were also derived for compositions, with which the waste reduction ratio was formulated as a function of the system parameters, to show usage of this model for theoretical understanding of the relationship between parameters and performances of the system. A numerical code for this mathematical model was developed. For a simplified equilibrium cycle, sensitivity and constrained optimization of the toxicity reduction ratio with respect to the system parameters were investigated by using the present model and code. It appears that the most important parameter to minimize waste toxicity is the separation efficiency at reprocessing. High fuel enrichment is beneficial because it expands the parametric space within the constraints. Also, depending on the constraints that apply, either the irradiation time or the fraction of core reprocessed at each cycle will be the second most important parameter.