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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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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?
R. L. Klueh, D. A. Canonico
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 353-367
Technical Paper | Material | doi.org/10.13182/NT77-A31949
Articles are hosted by Taylor and Francis Online.
The creep-rupture properties of a cylindrical Type 304 stainless-steel forging weld overlaid with Type 308 stainless-steel weld metal were evaluated. Tests were made at 755, 811, and 866 K on tangential and radial (relative to the axis of the forging cylinder) specimens taken from the weld metal, from the forging as forged, and the forging adjacent to the weld metal/forging interface. Two types of axial specimens were also tested: specimens taken from the unaffected forging and specimens taken across the fusion line. These latter specimens contained both weld metal and forging in the specimen gauge section. At all temperatures, the rupture strength of the forging immediately adjacent to the fusion line was greater than that of the forging specimens taken at a distance from the fusion line. All forging specimens were stronger than the Type 308 stainless steel of the overlay weld metal. The only effect of orientation was found for the overlay weld metal, where the tangential specimens had a slightly greater rupture life than the radial specimens. (The minimum creep rates for the two orientations were similar.) At 811 and 866 K, the ductilities of the overlay weld metal continuously decreased with increased rupture life. A minimum was found for the ductility-rupture life relationship of the Type 304 stainless-steel forging specimens at 866 K, while at 811 K, the ductility continuously decreased with increased rupture life.