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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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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.
V. A. Kazakov, A. S. Pokrovsky, A. V. Smirnov
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 392-406
Technical Paper | Nuclear Fuel Cycle Education Module / Material | doi.org/10.13182/NT81-A32648
Articles are hosted by Taylor and Francis Online.
The effect of neutron irradiation on the mechanical properties, structure, and peculiarities of void formation in the Mo-Zr-B alloy within the temperature range from 400 to 1080° C and fluences (1.3 to 11.5) · 1025 n/m2 (>0.1 MeV) has been investigated. The results from radiation studies of poly- and monocrystalline molybdenum, Mo—0.12 Zr—0.16 Ti alloy and of the Mo-Zr-B alloys with different initial thermal treatment have been analyzed. At temperatures of 950 and 1080°C, the voids of nonequiaxial shape are formed, and at 1010°C only planar defects, supposedly thin precipitates, are observed. These results show a minimum swelling of the Mo-Zr-B alloy at 1010°C. It is expected that the peculiarities of void evolution in the Mo-Zr-B alloy are due to the impurity precipitation on void faces. A good correlation of the calculated and experimental values for radiation strengthening of the alloy as a result of voids and dislocation loops within a wide range of their sizes and concentrations was observed. A connection was found between the reduction of the uniform elongation within the temperature range from 400 to 900° C and voidage parameters. A maximum strengthening of the alloy takes place after irradiation at 635°C, which results from a high density of both 1.5-nm-diam voids and the dislocation loops.
