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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Nuclear Technology
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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.
John R. Phillips
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 282-290
Technical Paper | Technique | doi.org/10.13182/NT76-A31569
Articles are hosted by Taylor and Francis Online.
The method for the nondestructive determination of two-dimensional radial isotopic distributions of fission and activation products of irradiated fuel pins was improved. In this method the fuel pins are gamma-scanned diametrally at two or more angular orientations, and the diametral isotopic scans are unfolded into two-dimensional radial isotopic distributions. The computer code for processing the data was improved so that it calculates the individual diametral volume segments, the source self-attenuation factors, and the source intensity matrices. The two-dimensional source intensity matrices are presented as radial isotopic distributions, density plots, contour plots, and isometric projections. The new computer code improves the precision and reduces the analysis time as shown in the examination of more than 10 experimental fast-reactor fuel pins.
