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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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?
B. C. Syrett, D. Cubicciotti, R. L. Jones
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 628-641
Technical Paper | Material | doi.org/10.13182/NT81-A32808
Articles are hosted by Taylor and Francis Online.
Four lots of stress-relieved Zircaloy-2 tubing were prepared from a single heat of the alloy. Tube reduction parameters were controlled so that each lot had a different crystallographic texture. The tubing with the most radial (least tangential) basal pole intensity was shown to have a Kearns texture number in the radial direction of 0.61, whereas the equivalent value for the tubing with the least radial texture was 0.48. Each lot of tubing was given one of three surface treatments: etched, etched and grit blasted, or lightly etched and shot blasted. The iodine stress corrosion cracking (SCC) susceptibility of the unirradiated tubing was determined by measuring the time to failure in a standard tube pres-surization test at ~593 K in which 6 mg of iodine was present for each square centimetre of exposed Zircaloy surface. The results showed that texture has a large effect on SCC susceptibility and that surface condition has a significant but lesser effect. The SCC resistance was lowest in the material with the most tangential basal pole intensity and increased as the texture became more radial. The lightly etched and shot-blasted surface resulted in times to failure that were shorter than the times for the other two surface conditions. However, it seems likely that the influence of surface treatment is quite complex and that SCC susceptibility can change significantly with a seemingly minor change in the surface treatment technique. The effect of texture was interpreted in terms of its influence on strength, on deformation characteristics, and on orientation of SCC susceptible planes with respect to the dominant tensile (hoop) stress. The effect of surface condition was interpreted in terms of its influence on residual stresses, on local texture changes, on local stress concentration, and on chemical activity.