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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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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
R. G. Hart, M. Lounsbury, R. W. Jones, M. J. F. Notley
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 6-17
Technical Paper | doi.org/10.13182/NSE64-A18137
Articles are hosted by Taylor and Francis Online.
A study of five methods of determining burnup in fuel test specimens has been made to determine the confidence which can be placed in the burnup numbers so obtained. The five methods compared are (1) uranium-235 depletion, (2) cobalt monitoring, (3) cesium-137 production, (4) plutonium production, and (5) calorimetry. The study includes a comparison of data obtained on portions of the specimen with that obtained on the complete specimen. It has been found that all of the methods give burnup values that are within ± 5% of the “best” burnup value, the “best” value being defined as the unweighted average of all the available results on a particular sample. The limitations and pitfalls of all the methods are discussed in some detail. It has further been found that a complete cross-section of the test specimen, approximately ½in. long, is sufficient sample to give representative burnup data. The integration from this to the complete specimen is relatively straightforward. Any sample not comprising a complete cross-section involves radial as well as longitudinal integration, giving results that are relatively uncertain, particularly in samples of high heat rating where migration of some species is a distinct possibility.