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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.
Pui Kuan, James L. Anderson, E. L. Tolman
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 977-989
Late Paper | TMI-2: Decontamination and Waste Management / Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A27690
Articles are hosted by Taylor and Francis Online.
Thermal interaction during the Three Mile Island Unit 2 2-B coolant pump transient is considered as an explanation of the partial melting of the plenum assembly. The primary system pressure response is used to calculate the energy transferred from the reactor core to the coolant and the steam generation rate during the pump transient. The steam generation rate is then used to calculate the heating of the plenum assembly. An energy balance indicates that exothermic oxidation of Zircaloy by steam must have taken place. In calculations of plenum assembly heating, the thermal emissivity of steam is reduced to simulate the effect of hydrogen generated during the oxidation process. It is determined from the calculations that in the presence of an appreciable amount of hydrogen (∼60%), only the thin structures at the lower end of the plenum assembly would have melted, while the relatively thick structures would have been partially ablated. These results are consistent with the observed damage.