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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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NEA panel on AI hosted at World Governments Summit
A panel on the potential of artificial intelligence to accelerate small modular reactors was held at the World Governments Summit (WGS) in February in Dubai, United Arab Emirates. The OECD Nuclear Energy Agency cohosted the event, which attracted leaders from developers, IT companies, regulators, and other experts.
L. L. Briggs, E. E. Lewis
Nuclear Science and Engineering | Volume 75 | Number 1 | July 1980 | Pages 76-87
Technical Paper | doi.org/10.13182/NSE80-A20320
Articles are hosted by Taylor and Francis Online.
A new two-dimensional coarse mesh technique for neutron transport calculations, the constrained finite element method, is formulated and applied to a series of nonuniform lattice problems. Finite elements in space and in angle are applied to the variational form of the even-parity transport equation. Spatial and angular constraints on the finite element trial functions along the intercell boundaries lead to a two-step solution procedure in which a global calculation yields the scalar flux values at coarse mesh nodes located on the intercell boundaries. The flux distributions and reaction rates within each cell are then found in terms of the nodal scalar flux values on the cell boundaries. The method is applied to a series of one-group fixed-source lattice problems, and the results are compared to those obtained from unconstrained finite element reference solutions and/or from response matrix solutions.