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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
Mohamed Dahmani, Robert Roy
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 236-249
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE155-236
Articles are hosted by Taylor and Francis Online.
The design of new generations of nuclear reactors will involve fine representations of the theoretical models. Advanced computational methods capable of solving large-scale problems dealing with large and complex systems are required. Therefore, the solution to challenging large-scale neutron transport problems is becoming more and more pressing in nuclear engineering applications. The increase in high-performance computing resources have made possible direct application of transport methods to large-scale computational models. However, many numerical acceleration techniques common to lattice transport codes are not applicable to three-dimensional geometries with heterogeneous material zones, especially for the eigenvalue problems with high-dominance scattering ratio. Consequently, large heterogeneous reactor problems have remained computationally intensive and impractical for routine engineering applications. One of the alternatives is to use high-performance computing methods to solve such problems in reasonable time.In this context, we propose an approach based on high-performance computing techniques to solve large-scale neutron transport problems using a three-dimensional characteristics method. A performance model is then introduced to analyze the three-dimensional characteristics solvers in the context of hybrid shared/distributed memory modern architectures. Several numerical results and discussions are presented including a scalability analysis done to predict the performance on a large number of processors.