ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
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.
M. Michelini
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 532-539
Technical Paper | doi.org/10.13182/NSE78-A27183
Articles are hosted by Taylor and Francis Online.
In the framework of the solution of the transport equation by means of diffusion techniques, an iterative procedure is presented that permits us to calculate the point-dependent diffusion coefficient, Dk(k = x,y,z), using standard diffusion codes. Numerical comparisons show that this procedure attains a flux distribution much closer to the transport distribution after one iteration than the classical diffusion flux. The time of the calculation is about twice that required by classical diffusion.
