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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
P. E. Gethard, L. R. Zumwalt
Nuclear Technology | Volume 3 | Number 11 | November 1967 | Pages 679-685
Technical Paper and Note | doi.org/10.13182/NT67-A27903
Articles are hosted by Taylor and Francis Online.
The diffusion of strontium and cesium through thin layers (100 μm) of isotropic pyrolytic carbon has been measured over the temperature range 1000 to 1700°C. Diffusion coefficients observed for cesium are orders of magnitude lower than those for strontium. The diffusion rates for both series are much lower than those observed in porous poly crystalline graphite, where little difference is seen between cesium and strontium. When constant chemical potential sources are used, chemical- and self-diffusion measurements for strontium give identical results in the Sr concentration range 0.01 to 0.2 wt%. There is apparently no concentration effect for cesium over the range 1.0 × 10−5 to 0.15 wt%. The difference between strontium and cesium diffusion in pyrolytic carbon is attributed to the greater steric effect of the pyrolytic-carbon defect structure relative to cesium.