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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Jan 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
February 2026
Nuclear Technology
January 2026
Fusion Science and Technology
November 2025
Latest News
ORNL to partner with Type One, UTK on fusion facility
Yesterday, Oak Ridge National Laboratory announced that it is in the process of partnering with Type One Energy and the University of Tennessee–Knoxville. That partnership will have one primary goal: to establish a high-heat flux facility (HHF) at the Tennessee Valley Authority’s Bull Run Energy Complex in Clinton, Tenn.
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.