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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
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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Latest News
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.
Raymond E. Alcouffe, Robert W. Albrecht
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 1-13
Technical Paper | doi.org/10.13182/NSE70-A21166
Articles are hosted by Taylor and Francis Online.
An approximation method is developed which is applicable to the solving of integro-differential equations using a digital computer. This method is a generalization of the finite difference method in that information about the expected solution is added as trial solutions. This allows the possibility of significantly reducing the number of discrete mesh points necessary to achieve an accurate solution over that required by the conventional finite difference method. The method is demonstrated on some space-time reactor kinetics problems.