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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
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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. Nakano, H. Tsunoda, J. Hirota
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 283-294
Technical Paper | doi.org/10.13182/NSE84-A17783
Articles are hosted by Taylor and Francis Online.
An experimental study has been made on FCA Assembly VIII-2 to test the validity of the calculational method for the reactivity effect due to axial displacement of fuel and cladding. The emphasis was placed on the systematic measurement of reactivity change and flux distribution in simple configurations rather than the simulation of a possible accident sequence. The analysis was made using the Japan Atomic Energy Research Institute Fast Set Version II. The transport calculation with an S4P0 approximation predicts both the reactivity change and the fission rates of 235U and 238U fairly well, although there still remains the trend of underestimation of reactivity effect, which increases with expansion of the fuel slumping to the core edge.
