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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
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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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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?
Bernd A. Thiele, Hermann Diehl, Wilhelm Ohly, Heinz Weber
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 597-606
G. Irradiation Behavior | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33481
Articles are hosted by Taylor and Francis Online.
Control rods in a pebble-bed-type high-temperature reactor operate at temperatures below 650°C, but in upset conditions short-term excursions up to 850°C can occur. Here, austenitic steels or nickel-base alloys show ductility losses caused by “helium high-temperature embrittlement.” The first of a series of irradiation experiments, followed by postirradiation tensile testing, quantified the losses in ductility of eight alloys (austenitic steels and high-temperature iron- and nickel-base alloys). Relative to the initial values of the rupture elongation, the ductility losses between 600 and 850°C were the same for all alloys with the exception of the strongly precipitation-hardened alloys, which showed more severe embrittlement at 600 to 700°C. The objective of the second experiment was to optimize the microstructure of austenitic steels (1.4981 and 1.4970) by specific thermomechanical treatments to increase the ductility after irradiation. Here again, it was found that all varieties showed nearly the same relative embrittlement behavior. Thus, it can be concluded that maximum ductility after irradiation requires a material with high ductility before irradiation.