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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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?
W. R. Johnson, L. D. Thompson, Thomas A. Lechtenberg
Nuclear Technology | Volume 66 | Number 1 | July 1984 | Pages 88-101
A. Selection, Production, and Development of Alloys for HTGR Component | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33458
Articles are hosted by Taylor and Francis Online.
The utilization of the high-temperature gas-cooled reactor (HTGR) for advanced or process heat applications will require the use of wrought components operating at temperatures up to 1000°C (1832°F) for times approaching 30 yr. Alloys for such components must withstand the corrosive effects (carburization and oxidation) of the impure helium primary coolant environment and maintain adequate elevated temperature strength. Commercially available wrought alloys have been found to be seriously limited for such applications because of their inherently poor resistance to corrosion in impure helium. As one approach to the solution of this problem, a program has been initiated to develop wrought alloys having a better combination of corrosion resistance and high-temperature strength, under advanced HTGR conditions, than commercial alloys currently available. This program culminated in 1980 with the design, melting, and fabrication of ten experimental Ni-Cr-Mo-W-Al-Ti-Zr-C alloys and with the initiation of efforts to evaluate their corrosion and mechanical behavior. Results of tests showed that all the experimental alloys exhibited superior carburization resistance in advanced reactor helium. In addition, several of the alloys exhibited excellent mechanical properties, including, in the case of one alloy, creep rupture strength at 900°C (1652°F), significantly better than that of the commercial alloy Inconel-617.
