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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.
Carlos Gago B.
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 55-64
Technical Paper | doi.org/10.13182/NSE79-A21285
Articles are hosted by Taylor and Francis Online.
It is shown that Fick's law can be used in the calculation of the rigorous neutron slowing down length for hydrogenous moderators (or in fact for any moderator), provided that the corresponding diffusion coefficient is determined within the set of equations of the consistent P1 approximation. For a given moderator, this coefficient depends solely on lethargy and source spectrum and therefore can be evaluated prior to an actual numerical calculation, which can then be carried out within the simplicity of a diffusion approximation. Furthermore, the flux calculated in this way essentially agrees with the consistent P1 result in all regions where this approximation is justified. The practical generalization to nonhydrogenous moderators is carried out by means of the Goertzel-Greuling procedure.