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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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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.
Selim Sancaktar, David R. Sharp
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 315-318
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34215
Articles are hosted by Taylor and Francis Online.
Probabilistic risk assessment (PRA) techniques and the lessons learned from previous PRA studies were used to evaluate the effectiveness of various design alternatives for the Westinghouse advanced pressurized water reactor design. This evaluation was done successfully at the design stage prior to the licensing stage and is probably the first example of such an application for a nuclear power plant design. Three measures of risk were utilized: plant core melt frequency per year, severe fission product release frequency per year, and economic risk to the plant owner in terms of present-day dollars. All plant configurations considered met or exceeded the safety criteria associated with regulatory requirements. The comparison of different alternatives was performed iteratively; after each iteration, the system most effective in reducing the total plant core melt frequency was chosen and added to the base plant configuration. The iterations were terminated when a predetermined cutoff level was reached. Probabilistic risk assessment techniques provide a viable method to create additional decision-making information at the plant design stage.