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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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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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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.
R. C. Kern, M. V. Bonaca
Nuclear Technology | Volume 9 | Number 6 | December 1970 | Pages 796-806
Fuels Cycle | doi.org/10.13182/NT70-A28711
Articles are hosted by Taylor and Francis Online.
Two models which are designed to perform fuel inventory calculations without the use of detailed and expensive computer programs have been developed. The accuracies of these models have been evaluated by comparing results obtained with them to measurements of discharged fuel from the Yankee Rowe reactor. In general, the models predict the 235U depletion to within ±2% of the measured values and the total plutonium production to within ±5% for fuel batches consisting of about 70 fuel assemblies. Uncertainties in the computational results have been ascertained to be about ±2% for the total 235U content and ±3% for the total plutonium production.