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Division Spotlight
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.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
D. Stöver, R. Hecker
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 465-474
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31906
Articles are hosted by Taylor and Francis Online.
Release data of cesium in Biso low-temperature isotropic (LTI) and high-temperature isotropic (HTI) coated particles are presented. Experimental and theoretical methods are briefly discussed. From the analysis of our experiments, kernel diffusion coefficients are calculated covering the kernel burnup range from 0.2 to 16% FIMA. At FIMA values ≥5%, cesium release is governed by the relatively low activation energy of ∼19 kcal/mole (79.6 kJ/mole), and even at temperatures as low as ∼900°C (1173 K), kernel retention remains low. The outer pyrocarbon layer acts as the release rate controlling barrier for both LTI and HTI coatings. Diffusion coefficients in the temperature range from 1000 to 1500°C (1273 to 1773 K) for LTI coatings and 1250 to 1600°C (1523 to 1873 K) for HTI coatings have been derived and lead to the following Arrhenius equations: On the basis of these data, releases for high-temperature-reactor cores can be calculated.