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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Contractor selected for Belgian LLW/ILW facility
Brussels-based construction group Besix announced that is has been chosen by the Belgian agency for radioactive waste management ONDRAF/NIRAS for construction of the country’s surface disposal facility for low- and intermediate-level short-lived nuclear waste in Dessel.
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.