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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.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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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.
B. L. Harbourne, M. S. Beck, J. P. Foster, A. Biancheria
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 156-170
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31183
Articles are hosted by Taylor and Francis Online.
An LMFBR fuel rod performance analysis system has been developed using the CYGRO-F computer code. The approach used was to model materials properties and phenomena using basic data and fundamental formulations as far as possible. Lack of data and understanding prevent a completely fundamental solution. The uncertainties were resolved by normalizing the code against selected experimental results and making appropriate adjustments to the models. The result of this work is an analytical system of models integrated into a central stress-strain analysis. Application of the system to independent experimental data gave satisfactory agreement between analysis and observation. Four highly significant models have emerged from this work. The analytical fuel swelling model simulates volume increase saturation and subsequent volume conservate growth which can result in center-hole growth independent of pore migration. The feasibility of a fundamental fuel swelling model has been demonstrated. This model describes the nucleation, growth, and migration of gas bubbles and produces mechanical effects similar to those in the analytical model. The cladding swelling model accounts for the effects of stress on swelling rate to reproduce the large volume changes observed in some fuel rod cladding. The results of this model are in qualitative agreement with fundamental analyses of the effect. Studies of startup and early life behavior resulted in a thermomechanical analysis system which describes in detail the complex interacting phenomena occurring under these transient conditions. The system may be applied to the determination of LMFBR core limiting operating conditions.