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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Karl Erickson, N. J. Mccormick, Gene L. Woodruff
Fusion Science and Technology | Volume 1 | Number 4 | October 1981 | Pages 533-541
Technical Paper | Hybrid Reactor | doi.org/10.13182/FST81-A19946
Articles are hosted by Taylor and Francis Online.
The feasibility of spatial and temporal power density flattening in fusion-fission hybrid reactors was investigated by varying the concentration of 239Pu within a set of zones in the fission region and by examining two different fuel management schemes. Blanket designs with no 239Pu typically had a spatial maximum-to-average power density ratio of ∼2.5, but this value was reduced to between 1.26 and 1.67, depending on the design and fuel management scheme selected. Unfortunately, however, significant impact occurs only with relatively high fissile concentrations, with the outer zones approaching equilibrium values. Thus, either an impractically large fissile inventory for startup or long operating histories would be required.
