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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
E. E. Bloom, J. M. Leitnaker, J. O. Stiegler
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 232-243
Technical Paper | Material | doi.org/10.13182/NT76-A31685
Articles are hosted by Taylor and Francis Online.
The effects of titanium additions up to 0.6 wt% on the irradiation-induced swelling and changes in creep-rupture properties were investigated. Samples were irradiated in the Experimental Breeder Reactor II at temperatures in the range from 450 to 700°C to a maximum neutron fluence of 7.8 × 1026 n/m2 (>0.1 MeV). In annealed material, the irradiation-induced swelling exhibited a minimum in the range 0.2 to 0.4 wt% titanium. The minimum in swelling was directly attributable to a minimum in the concentration of voids. Samples irradiated in the 20% cold-worked condition exhibited slight densification at 3.0 × 1026 n/m2 (>0.1 MeV) at both 500 and 600°C. A small density decrease (0.23%) occurred during irradiation to 6.6 × 1026 n/m2 (>0.1 MeV). Postirradiation creep-rupture ductility was a maximum for alloys containing 0.23 and 0.33 wt% titanium. The observed swelling behavior in the annealed material is thought to be associated with changing amounts of titanium and carbon in solution in the austenite as the total titanium concentration is increased. The improved ductility is attributable to a decreased tendency for grain boundary crack formation and appears to be associated with removal of sulfur and possibly other impurities from solution in the austenite.
