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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
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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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.
J. Bentley, F. W. Wiffen
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 376-384
Technical Paper | Uranium Resource / Material | doi.org/10.13182/NT76-A31651
Articles are hosted by Taylor and Francis Online.
Vanadium-base alloys, V—10% Cr, V—20% Ti, and VANSTAR-7, alloys with potential for fusion reactor application, have been irradiated in the Experimental Breeder Reactor II in the temperature range of 400 to 800°C, mainly to a fluence of 1.5 × 1022 n/cm2 (>0.1 MeV). Swelling determined both from immersion density measurements and void distribution data obtained by transmission electron microscopy showed that the V—20% Ti was completely resistant to void formation for these irradiation temperatures and for the highest fluence achieved, 6 × 1022 n/cm2. Voids formed in both the V—10% Cr and VANSTAR-7 alloys, but only the V—10% Cr, irradiated at 690 and 805° C, showed technologically significant swelling, near 1%. Swelling in this alloy at lower temperatures and in VANSTAR-7 at all temperatures was below 0.1%. Dislocation structures were complex in all three alloys. In the V—20% Ti, the scale of the dislocation network coarsened with increasing irradiation temperature. In the other two alloys, the scale of the damage, both dislocation and void components, was similar for irradiation at 496 and 580°C, but coarsened considerably to produce similar structures for irradiations at 690 and 805°C. In many cases, detail of the microstructure was obscured by strongly diffracting zones that are believed to be impurity related. Of the three alloys examined, V—20% Ti possesses the greatest swelling resistance for the irradiation temperatures and fluences achieved and thus is judged to have the greatest potential for use in fusion reactors.