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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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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.
C. J. Mueller, J. K. Vaurio
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 264-278
Technical Paper | doi.org/10.13182/NSE79-A20616
Articles are hosted by Taylor and Francis Online.
This paper describes the basic equations and solution techniques of a collection of heat transfer and coolant voiding dynamics models that have been developed and successfully applied to simulate hypothetical accidents in liquid-metal-cooled fast breeder reactors (LMFBRs) to the point of permanent subcriticality or to the initiation of a prompt-critical excursion. These models emphasize analytic and integral solution techniques to minimize computational time and have been programmed into the SACO fast-running accident analysis computer code. The comparisons of SACO results to analogous SAS3D results used to qualify these models are illustrated and discussed. The fast-running nature of these models makes them an ideal sensitivity analysis tool for use in probabilistic evaluations of LMFBR accidents. Their use in this application is illustrated.