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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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?
K. Röllig
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 516-523
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31912
Articles are hosted by Taylor and Francis Online.
The release of the rare fission gases, krypton and xenon, from a high-temperature reactor pebble-bed core is predominantly determined by the heavy-metal contamination of the matrix material during manufacture. In the case of the Thorium High-Temperature Reactor prototype fuel, particles with failed coatings contribute <10% to the total core release of the xenon and krypton isotopes with the exception of long-lived 85Kr. In a series of irradiation experiments with spherical fuel elements, a linear relation between the gas release and the contamination of the matrix material was established. At mean fuel temperatures of 700°C (973 K), only ∼1% of the 85mKr and 133Xe produced by fuel contamination is released. The experimental data for the steady-state release of 13 krypton and xenon isotopes can be explained by describing the graphitic matrix material as a two-component. system. Component 1 is attributed to the graphitic grains of the raw material, and component 2 to the material between the grains, such as the amorphous, nongraphitized binder coke. The total contamination-induced release from the fuel elements is given by the retention characteristics of the two components working in parallel, followed in series by the gas-phase transport through the interconnected porosity of the fuel element structure. As a consequence of this model, the apparent activation energy for the steady-state release depends on the half-lives of the isotopes of the same species yielding, e.g., 5 kcal/mole (21 kJ/mole) for 140Xe and 9 kcal/mole (38 kJ/mole) for 138Xe.