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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.