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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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.
M. Antonopoulos-Domis, C. Housiadas
Nuclear Science and Engineering | Volume 132 | Number 3 | July 1999 | Pages 337-345
Technical Paper | doi.org/10.13182/NSE99-A2068
Articles are hosted by Taylor and Francis Online.
Estimation of the moderator temperature coefficient (MTC) of reactivity of pressurized water reactors by noise analysis is investigated, both theoretically and through numerical simulations. It is found that using local neutron signals, all estimators of MTC will underestimate the actual MTC value, as indeed is observed in all measurements reported in the literature. However, the relative deviation from the actual MTC value remains practically constant over a wide range of MTC values. This suggests that it is possible to calibrate the estimate at the beginning of the fuel cycle and then use this calibration until the end of the fuel cycle. A new estimator is proposed based on integral (point model) concepts. This estimator is found capable of providing the actual value of MTC, provided that coolant velocity fluctuations are at least as strong as coolant inlet temperature fluctuations in inducing neutron and coolant temperature fluctuations.