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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
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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May 2025
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Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
Shungo Iijima, Tadashi Yoshida, Tohru Yamamoto
Nuclear Technology | Volume 80 | Number 2 | February 1988 | Pages 263-268
Technical Paper | Advanced Light Water Reactor / Fission Reactor | doi.org/10.13182/NT88-A34050
Articles are hosted by Taylor and Francis Online.
A high precision fission product model for boiling water reactor (BWR) lattice calculation was developed, which consists of 45 nuclides to be treated explicitly and one nonsaturating pseudo nuclide. This model is applied to a high conversion BWR lattice calculation code. From a study based on a three-energy-group calculation of fission product poisoning due to full fission products and explicitly treated nuclides, the multigroup capture cross sections and the effective fission yields of the pseudo nuclide are determined, which do not depend on fuel types or reactor operating conditions for a good approximation. Apart from nuclear data uncertainties, the model and the derived pseudo nuclide constants would predict the fission product reactivity within an error of 0.1% Δk at high burnup.