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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.
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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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Suresh V. Garimella, Richard N. Christensen
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 388-398
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34377
Articles are hosted by Taylor and Francis Online.
An experimental investigation was undertaken in which transient condensation of steam-air mixtures occurred on one face of a large aluminum block of which all the other faces were insulated. Tests were conducted in a pressure vessel at pressures of up to 650 kPa. The transients were provided by a sudden increase in the vessel pressure from a given value to a much higher value by the introduction of additional steam. Temperature measurements within the block agreed well with results from a finite difference analysis of the condensing surface and block. Visual observation of the condensing surface indicated that the mode of condensation was predominantly dropwise. The dependence of the heat transfer coefficient on time, pressure, severity of the transient, percentage of noncondensables, and the driving temperature difference was studied. The results at the much higher pressures and transient conditions used in this study agreed with observations in the literature of such trends at lower pressures. There was evidence of the occurrence of a buildup of noncondensables at the condensing surface with time.