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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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February 2025
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Latest News
Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
D. G. Harman
Nuclear Technology | Volume 9 | Number 4 | October 1970 | Pages 561-571
Material | doi.org/10.13182/NT70-A28766
Articles are hosted by Taylor and Francis Online.
Tensile and creep-rupture data have been obtained at 700 and 760°C for several experimental heats of lncoloy 800 that were irradiated in the Oak Ridge Research Reactor (ORR) at elevated temperatures or held at control temperatures in the laboratory. Effects of composition, grain size, and stress level (or strain rate) on these strength properties were investigated. Enhanced postirradiation ductility was observed in Incoloy 800 containing ∼0.1% Ti in creep-rupture tests. The maximum ductility for this composition was obtained in fine-grained specimens tested at low creep stress levels, and the ductility appeared to be unaffected by carbon content. The ductility of unirradiated material was also increased by decreasing either grain size or strain rate. Significant variations in properties (both control and postirradiation tests) were noted for alloys within the commerciallncoloy 800 specification range. The ductility peak at ∼0.1% Ti is not fully understood; it might be best explained by two independent mechanisms, one accounting for the increasing ductility with increasing titanium at levels less than 0.1% and the other explaining the decreasing ductility at higher titanium levels. The grain size effect may be due to differences in the distribution of helium and/or trace elements or to a grain-size dependent variation in stresses necessary for grain boundary fracture. Higher postirradiation ductility at lower stresses could be due to stress relaxation, grain boundary migration, or less pronounced stress-induced growth of helium bubbles present in the grain boundaries.