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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Latest News
Hanford proposes “decoupled” approach to remediating former chem lab
Working with the Environmental Protection Agency, the Department of Energy has revised its planned approach to remediating contaminated soil underneath the Chemical Materials Engineering Laboratory (commonly known as the 324 Building) at the Hanford Site in Washington state. The soil, which has been designated the 300-296 waste site, became contaminated as the result of a spill of highly radioactive material in the mid-1980s.
Changho Lee, Hansol Park, Yeon Sang Jung, Cooper Trucks
Nuclear Science and Engineering | Volume 199 | Number 1 | April 2025 | Pages S42-S55
Review Article | doi.org/10.1080/00295639.2024.2348855
Articles are hosted by Taylor and Francis Online.
High-fidelity deterministic steady-state simulations of the Empire microreactor problem were conducted using the discontinuous finite element method–based discrete ordinate solver in Griffin, accompanied by the online cross-section self-shielding application programming interface (SSAPI). The 68-group cross-section libraries for SSAPI were generated through a series of Python scripts and using a combination of Serpent2, NJOY, and MC2-3 with ENDF/B-VII.0, VII.1, and VIII.0 data. Additionally, the 27-group libraries were generated as well to improve computational performance while maintaining the solution accuracy. The capabilities of Griffin with these three ENDF/B cross-section libraries were rigorously tested across various Empire microreactor benchmark problems, including fuel assembly and two- and three-dimensional cores with control drums rotated in or out. The calculation results convincingly demonstrated that Griffin with the cross-section libraries and SSAPI achieves accurate simulations of the Empire microreactor cores, exhibiting accuracy in terms of eigenvalue, control drum reactivity worth, and pin power distribution when compared to corresponding Serpent2 solutions.