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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
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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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. M. Logan, T. T. Komoto
Nuclear Science and Engineering | Volume 115 | Number 1 | September 1993 | Pages 38-42
Technical Paper | doi.org/10.13182/NSE93-A35520
Articles are hosted by Taylor and Francis Online.
Experimentally observed 14-MeV neutron removal cross sections are presented for 16 materials. At a scattering energy loss of 4 MeV, the effective macroscopic cross section per unit mass (in square centimetres per gram) for a nucleus of mass A is given by 0.25A -1.78 + 0.10A-0.47. Such information provides a simple method for estimating neutron transport in systems driven by thermonuclear neutrons.
