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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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Latest News
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
Akio Yamamoto, Masahiro Tatsumi, Naoki Sugimura
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 144-151
Technical Paper | doi.org/10.13182/NSE08-80
Articles are hosted by Taylor and Francis Online.
A new burnup calculation method, called the projected predictor-corrector (PPC) method, is proposed. In comparison with the conventional predictor-corrector (PC) method, a larger time-step size can be used in burnup calculation without losing calculational accuracy. The PPC method is especially useful for Gd-bearing fuel assemblies, for which a fine time step size is necessary in burnup calculations. The PPC method utilizes a correlation between the number density and the reaction rate in each burnable nuclide and improves the accuracy of the microscopic reaction rate in the corrector step by estimating the “projected” reaction rate. The additional computation time for the PPC method is negligible. Verification calculations are performed for 17 × 17 pressurized water reactor fuel assemblies with 16 Gd-bearing fuel rods. The content of Gd in Gd-bearing fuel rods is set to be 2 to 10 wt%. The calculation results indicate that the PPC method shows comparable accuracy to conventional PC methods whose step time size is about half; i.e., the number of burnup steps in the PPC method can be reduced to about half of that in the conventional PC method.