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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
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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Latest News
TVA to file for Clinch River SMR construction permit by June
In a Q&A posted on TVA’s website last week about a “new nuclear heyday,” Bob Deacy shared his vision for the Clinch River nuclear site in Oak Ridge, Tenn.—and some news about next steps for the company’s small modular reactor plans.
The Tennessee Valley Authority’s senior vice president for the Clinch River project, Deacy described his vision for up to four SMRs built on plots smaller than a football field with state-of-the-art digital equipment and a newly trained workforce providing reliable 24/7 power to the grid.
Sunday, April 27, 2025|8:00AM–5:00PM MDT
Horace Tabor
Cost: $99
Limited Space
Organizer: Paul Romano (Argonne National Laboratory), Micah Gale (Idaho National Laboratory) and Travis Labossiere-Hickman (Idaho National Laboratory)
This workshop will introduce attendees to two powerful Python-based tools for performing Monte Carlo simulations. The first tool that will be covered is MontePy, a Python library for reading, editing, and writing MCNP input files. Through hands-on demonstrations, we will show methods to automate common tasks for updating large MCNP models as well as ways to create an MCNP problem from scratch in MontePy. After covering MontePy, we will then proceed with an interactive demonstration of the OpenMC Monte Carlo code, showing how its Python API can be used to define a model, run a simulation, and analyze the results. Together, attendees will have a strong starting point for performing their own explorations using MontePy and OpenMC.
Participants should bring their laptop to follow along with the live demonstrations. There are no requirements to install software ahead of time. A link will be provided to access the software on a cloud computing platform accessible through any web browser.
