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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
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.
T. J. Costello, R. L. Laubham, W. R. Miller, C. R. Smith
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 174-180
Technical Paper | Instruments | doi.org/10.13182/NT73-3
Articles are hosted by Taylor and Francis Online.
An eddy-current flowmeter (ECFM), designed to measure the velocity of coolant sodium exiting the fuel subassemblies of the Fast Flux Test Facility (FFTF) to be built at Richland, Washington, was tested in the Westinghouse Advanced Reactors Division’s General Purpose Loop No. 2 (GPL-2) during the period of October 2, 1971 to March 16, 1972. The ECFM was operated in both a wet and dry prototypic (FFTF) design test housing. In the wet design test housing, the ECFM is exposed directly to sodium; in the dry design test housing, the ECFM is shielded from sodium by a stainless-steel “thimble.” During both tests, the same ECFM electronics supply and associated wiring were used. The same ECFM electrical adjustments also were employed in both cases. Throughout the total testing period of 1351.6 h, the ECFM operated satisfactorily. No failures or malfunctions occurred in the ECFM, its power supply, or the three test thermocouples. Significantly, the data showed that the ECFM’s overall average dc output signal in the dry design was 62% of that in the wet design.
