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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
Stefano Passerini, Mujid S. Kazimi, Eugene Shwageraus
Nuclear Science and Engineering | Volume 178 | Number 2 | October 2014 | Pages 186-201
Technical Paper | doi.org/10.13182/NSE13-20
Articles are hosted by Taylor and Francis Online.
Experience with modeling fuel cycle options reveals that the large amount of generated data makes it difficult to understand trade-offs among fuel cycle policies. This paper shows that numerical optimization can be used to better identify impacts of fuel cycle policies and condense the generated data against a few significant criteria. The once-through cycle is considered the baseline case, while advanced technologies with fuel recycling characterize the alternative fuel cycle options available in the future. The options include, among others, recycling the fissile materials from spent light water reactor fuel in fast reactors (FRs) as well as deployment of innovative recycling reactor technologies, such as the 235U initiated FRs. Additionally, a first-of-a-kind optimization scheme for the nuclear fuel cycle analysis is described. Optimization metrics of interest to different stakeholders in the fuel cycle (economics, fuel resource utilization, high-level waste, transuranic materials/proliferation management, and environmental impact) are utilized for two different optimization techniques: a linear one and a stochastic one. Stakeholder elicitation provided sets of relative weights for the identified metrics appropriate to each stakeholder group, which were then used to demonstrate feasibility of arrival at optimum fuel cycle configurations for recycling technologies. The stochastic optimization tool, based on a genetic algorithm, was used to identify noninferior solutions according to Pareto’s dominance approach to optimization. The main trade-off for fuel cycle optimization was found to be between emphasizing economics versus most of the other identified metrics.