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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
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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Latest News
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.
Jerome L. Shapiro
Nuclear Science and Engineering | Volume 12 | Number 4 | April 1962 | Pages 449-456
Technical Paper | doi.org/10.13182/NSE62-A26090
Articles are hosted by Taylor and Francis Online.
An experimental and analytical study of the void coefficient of reactivity in the Ford Nuclear Reactor (a fully enriched, swimming pool type) has been completed. A stream of air bubbles was used to introduce voids. Out-of-pile calibration of the air flow system was necessary to account for variation in bubble rise velocity with average air concentration. This method is extremely simple except for the calibration procedure. With the results presented in this paper, the void coefficients of other reactors with similar fuel elements (18 plate, BSR type) can be measured without the necessity for recalibration. For the calculation of uniformly distributed void coefficients, relatively simple two-group diffusion theory is shown to be accurate provided the variation of leakage in all three dimensions is taken into account. This variation of leakage is computed by the use of a buckling iterative procedure. Second order effects, such as the variation of effective thermal neutron temperature and disadvantage factor, may be neglected. For the calculation of localized void effects, the buckling iteration method is inaccurate due to the nonseparability of axial and radial flux distribution in this small core. To improve the accuracy an extension of this method to several region iteration is suggested. The principal value of this type of calculation is the short computer time required.