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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
From South Korea to Belgium: Testing a high-density research reactor fuel
The Korea Atomic Energy Research Institute has developed a high-density uranium silicide fuel designed to replace high-enriched uranium in research reactors. Recent irradiation tests appear to be successful, KAERI reports, which means the fuel could be commercialized to continue a key global nuclear nonproliferation effort—converting research reactors to run on low-enriched uranium fuel.
Nam Zin Cho, Seungsu Yuk, Han Jong Yoo, Sunghwan Yun
Nuclear Science and Engineering | Volume 175 | Number 3 | November 2013 | Pages 227-238
Technical Paper | doi.org/10.13182/NSE12-68
Articles are hosted by Taylor and Francis Online.
In current practice of nuclear reactor design analysis, the whole-core diffusion nodal method is used in which nodal parameters are provided by a single-assembly lattice physics calculation with the zero net current boundary condition. Thus, the whole-core solution is not transport, because the interassembly transport effect is not incorporated. In this paper, the overlapping local/global iteration framework that removes the limitation of the current method is described. It consists of two-level iterative computations: half-assembly overlapping local problems embedded in a global problem. The local problem can employ heterogeneous fine-group deterministic or continuous-energy stochastic (Monte Carlo) transport methods, while the global problem is a homogenized coarse-group transport-equivalent model based on partial current-based coarse-mesh finite difference methodology. The method is tested on several highly heterogeneous multislab problems and a two-dimensional small core problem, with encouraging results.