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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
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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Latest News
Nuclear materials testing project brings U.S. and U.K. expertise together
As nations look to nuclear energy as a source of reliable electricity and heat, researchers and industry are developing a new generation of nuclear reactors to fill the need. These advanced nuclear reactors will provide safe, efficient, and economical power that go beyond what the current large light water reactors can do.
But before large-scale deployment of advanced reactors, researchers need to understand and test the safety and performance of the technologies—especially the coolants and materials—that make them possible.
Now, the United States and the United Kingdom have teamed up to test hundreds of advanced nuclear materials.
Jin Feng Huang
Nuclear Science and Engineering | Volume 196 | Number 7 | July 2022 | Pages 873-885
Technical Paper | doi.org/10.1080/00295639.2021.2025299
Articles are hosted by Taylor and Francis Online.
The solitary wave naturally arises in many areas of mathematical physics, including in nonlinear optics, plasma physics, quantum field theory, and fluid mechanics. In the past few years, for an advanced nuclear energy system, a particular class of traveling wave reactor called the Constant Axial shape of Neutron flux, nuclide number densities and power shape During Life of Energy production (CANDLE) reactor has been proposed, and an analytical solution has been desired since it could reveal the global characters of the solution. In this study, from the perspective of the solitary wave, the analytical solution of this advanced nuclear energy system is demonstrated through coupling the one-group neutron diffusion equation with the burnup equation. The tanh-function method is applied to solve that nonlinear partial differential equation. The relationship between the velocity of the solitary wave, wave amplitude, or neutron flux and the evolution of the nuclide is revealed by the analytical method. The results demonstrate that the neutron flux is proportional to the wave velocity. The results also imply that the amplitude of the neutron flux is proportional to the square root of the diffusion coefficient but is inversely proportional to the initial 238U density.