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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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May 2025
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.
W. E. Downs
Nuclear Technology | Volume 5 | Number 2 | August 1968 | Pages 55-61
Technical Paper and Note | doi.org/10.13182/NT68-A27950
Articles are hosted by Taylor and Francis Online.
An improved 124Sb-Be neutron source was developed to give a thermal flux of 6 × 108 n/(cm2 sec) over a 20-cm3 volume with a uniformity better than ±4%. With a unit of this type, 90 radioisotopes with a specific activity of 0.1 µC/g can be produced. Because of the constancy of the flux, an analytical precision of ±1% is easily attainable. The present system will handle more than one sample transfer unit, allowing several simultaneous experiments or analyses. The pool system described here is a versatile research unit and not a general-purpose industrial analytical facility. Considering the features and costs of this 124Sb-Be source, it appears best suited for applications requiring a continuous thermal-neutron flux, such as an on-line system for industry.
